ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 100

DOE Review Release 08/02/2013

Document Title:

Assignment of Fission and Activation 

Product Radionuclides for Non-Specific 

Bioassays at Savannah River Site –

Comparison of Methods

Document Number: ORAUT-RPRT-0047

Revision: 00

Effective Date: 07/23/2013

Type of Document: Report

Supersedes: None

Subject Expert(s): Robert E. Burns, Jr., Donald E. Bihl, and Matthew G. Arno 

Approval: Signature on File Approval Date: 07/02/2013

Robert E. Burns, Jr., Document Owner

Concurrence: Signature on File Concurrence Date: 07/02/2013

John M. Byrne, Objective 1 Manager

Concurrence: Signature on File Concurrence Date: 07/02/2013

Edward F. Maher, Objective 3 Manager

Concurrence: Vickie S. Short Signature on File for Concurrence Date: 07/02/2013

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 07/23/2013

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 2 of 100

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

07/23/2013 00 New report to compare organ doses from an intake of fission 

products determined from urinalysis using the default guidance in 

Revision 03 of ORAUT-TKBS-0003, Savannah River Site (SRS Site 

Profile, p. 70) versus using an approach based on the method in 

ORAUT-OTIB-0054, Fission and Activation Product Assignment for 

Internal Dose-Related Gross Beta and Gross Gamma Analyses. 

This report also compares organ doses from an intake of 4,400 

dpm/d of mixed fission products using the radionuclide guidance 

mixture in Table 4.4.2-7 of the SRS Site Profile (p. 82) with organ 

doses from an intake of 4,400 dpm/d of fission products apportioned 

as recommended in OTIB-0054. This addresses an SRS Advisory 

Board Work Group issue regarding fission products. Incorporates 

comparisons of organ doses computed using the nine representative 

reactor cases from OTIB-0054 with five cases selected to represent 

production reactor operations at the Savannah River Site (SRS). 

Develops site-specific intake and activity fraction values to be used 

for evaluating SRS claims and draws comparisons of committed 

organ doses assigned using these new values with doses assigned 

using the guidance currently given in the SRS Site Profile. 

Incorporates formal internal and NIOSH review comments. Training 

required: As determined by the Objective Manager. Initiated by 

Robert E. Burns, Jr.
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 3 of 100

TABLE OF CONTENTS

SECTION TITLE PAGE

1.0 Introduction .............................................................................................................................. 9

2.0 Comparison of Organ Doses Computed Using the OTIB-0054 Representative 

Reactor Cases with Those Computed for the SRS Production Reactors................................ 10

2.1 OTIB-0054 Method..................................................................................................... 11

2.2 Reactors Considered in OTIB-0054 and in This Report .............................................. 11

2.3 Intake and Activity Fraction Data for the Five SRS Cases .......................................... 13

2.4 Organ Dose Calculations for the Representative Reactor and SRS Cases................. 13

2.5 Discussion of Organ Dose Comparisons Between the Representative 

Reactor and SRS Cases............................................................................................. 14

3.0 Development of SRS-Specific Activity Fraction Values for Assigning MFAP Intakes 

from Gross Beta and Gross Gamma Urinalyses..................................................................... 15

3.1 Radiochemistry for MFAP Urinalyses at SRS ............................................................. 15

3.2 Calculation of the SRS-Specific Activity Fractions for Gross Beta and Gross 

Gamma Urinalyses ..................................................................................................... 16

4.0 Committed Organ Doses Computed Using the SRS-Specific Activity and Intake 

Fraction Values ...................................................................................................................... 16

4.1 Committed Organ Doses for a Unit Urinary Excretion Rate of 1 Becquerel 

per Day....................................................................................................................... 17

4.2 Committed Organ Doses for an Intake Rate of 4,400 Dpm per Day............................ 17

5.0 Comparison of Doses Assigned Using the SRS-Specific Intake and Activity 

Fraction Values with Those Assigned per the SRS Site Profile .............................................. 18

6.0 Conclusions and Recommendations ...................................................................................... 18

6.1 Comparisons of the Representative Reactor and SRS Cases .................................... 18

6.2 Comparison Based on Beta Activity in Urine............................................................... 18

6.3 Comparison Based on Intakes.................................................................................... 19

6.4 Comparison to Test Case Whole Body Counts........................................................... 19

7.0 Recommendation................................................................................................................... 19

8.0 References ............................................................................................................................ 20

ATTACHMENT A, SRS RPRT-0047 EVALUATION .......................................................................... 66
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LIST OF TABLES

TABLE TITLE PAGE

2-1 ORIGEN-S irradiation parameters for the nine representative reactor cases.......................... 21

2-2 ORIGEN-S irradiation parameters for the five SRS cases...................................................... 21

2-3 Normalized intake fractions for the dosimetrically important radionuclides ............................. 22

2-4 Normalized intake fractions for the reduced list of dosimetrically important 

radionuclides..........................................................................................................................24

2-5 Associated radionuclide activity fractions for assigning intakes relative to 90Sr or 

137Cs ......................................................................................................................................25

2-6 Urine activity fractions for raw urine samples ......................................................................... 27

2-7 Urine activity fractions for urine samples after major chemical processing ............................. 27

2-8 Activity ratios for use if gross beta or gross gamma results are reported for air 

samples and workplace measurements ................................................................................. 28

2-9 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, minimally processed samples 

at 10 days decay....................................................................................................................29

2-10 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, minimally processed samples 

at 40 days decay....................................................................................................................30

2-11 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, minimally processed samples 

at 180 days decay..................................................................................................................31

2-12 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, minimally processed samples 

at 1 year decay ...................................................................................................................... 32

2-13 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, significantly processed 

samples at 10 days decay...................................................................................................... 33

2-14 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, significantly processed 

samples at 40 days decay...................................................................................................... 34

2-15 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, significantly processed 

samples at 180 days decay.................................................................................................... 35

2-16 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta urinalysis, significantly processed 

samples at 1 year decay ........................................................................................................ 36

2-17 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma urinalysis, minimally processed 

samples at 10 days decay...................................................................................................... 37

2-18 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma urinalysis, minimally processed 

samples at 40 days decay...................................................................................................... 38

2-19 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma urinalysis, minimally processed 

samples at 180 days decay.................................................................................................... 39

2-20 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma urinalysis, minimally processed 

samples at 1 year decay ........................................................................................................ 40

2-21 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta air samples at 10 days decay................................. 41
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2-22 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta air samples at 40 days decay................................. 42

2-23 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta air samples at 180 days decay ............................... 43

2-24 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross beta air samples at 1 year decay.................................... 44

2-25 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma air samples at 10 days decay ............................ 45

2-26 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma air samples at 40 days decay ............................ 46

2-27 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma air samples at 180 days decay .......................... 47

2-28 Comparisons of organ dose results for the OTIB-0054 representative reactor 

cases and the SRS cases for gross gamma air samples at 1 year decay............................... 48

3-1 SRS-specific chemical yield values for processed urine samples........................................... 49

3-2 IRFs and yield and counting adjustment factors for beta and gamma counts ......................... 50

3-3 SRS-specific urine activity fractions for 90Sr ........................................................................... 50

3-4 SRS-specific urine activity fractions for 95Zr............................................................................ 51

3-5 Associated radionuclide activity fractions for assigning intakes relative to 95Zr....................... 51

4-1 SRS-specific committed organ doses for 1 Bq/d in urine by gross beta at 10 days 

decay .....................................................................................................................................53

4-2 SRS-specific committed organ doses for 1 Bq/d in urine by gross beta at 

180 days decay......................................................................................................................54

4-3 SRS-specific committed organ doses for 1 Bq/d in urine by gross beta at 1 year 

decay .....................................................................................................................................55

4-4 Associated radionuclide activity fractions for assigning intakes, particulates only................... 56

4-5 Committed organ doses for a 4,400 dpm/d chronic intake rate at 10 days decay ................... 57

4-6 Committed organ doses for a 4,400 dpm/d chronic intake rate at 180 days decay ................. 58

4-7 Committed organ doses for a 4,400 dpm/d chronic intake rate at 1 year decay...................... 59

5-1 Comparisons of committed organ doses computed using the SRS Site Profile 

assumptions with those determined using the OTIB-0054 method for 1 Bq/d in 

urine by gross beta at 10 days decay..................................................................................... 60

5-2 Comparisons of committed organ doses computed using the SRS Site Profile 

assumptions with those determined using the OTIB-0054 method for 1 Bq/d in 

urine by gross beta at 180 days decay................................................................................... 61

5-3 Comparisons of committed organ doses computed using the SRS Site Profile 

assumptions with those determined using the OTIB-0054 method for 1 Bq/d in 

urine by gross beta at 1 year decay ....................................................................................... 62

5-4 Comparisons of committed organ doses computed using the SRS Site Profile 

assumptions with those determined using the OTIB-0054 method for a 4,400 

dpm/d chronic intake rate at 10 days decay ........................................................................... 63

5-5 Comparisons of committed organ doses computed using the SRS Site Profile 

assumptions with those determined using the OTIB-0054 method for a 4,400 

dpm/d chronic intake rate at 180 days decay ......................................................................... 64

5-6 Comparisons of committed organ doses computed using the SRS Site Profile 

assumptions with those determined using the OTIB-0054 method for a 4,400 

dpm/d chronic intake rate at 1 year decay.............................................................................. 65
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 6 of 100

LIST OF FIGURES

FIGURE TITLE PAGE

2-1 Steps and factors in determining beta counts in a urine sample from a given 

intake or in determining intake from beta counts .................................................................... 12

A-1 Worker 1 137Cs fit ...................................................................................................................67

A-2 Worker 1 144Ce predicted body burdens ................................................................................. 68

A-3 Worker 1 106Ru predicted body burdens ................................................................................. 69

A-4 Worker 1 95Zr/Nb predicted body burdens .............................................................................. 69

A-5 Worker 2 137Cs fit ...................................................................................................................70

A-6 Worker 2 144Ce predicted body burdens ................................................................................. 71

A-7 Worker 2 106Ru predicted body burdens ................................................................................. 71

A-8 Worker 2 95Zr/Nb predicted body burdens .............................................................................. 72

A-9 Worker 3 137Cs fit ...................................................................................................................72

A-10 Worker 3 144Ce predicted body burdens ................................................................................. 73

A-11 Worker 3 106Ru predicted body burdens ................................................................................. 74

A-12 Worker 3 95Zr/Nb predicted body burdens .............................................................................. 74

A-13 Worker 4 137Cs fit ...................................................................................................................75

A-14 Worker 4 144Ce predicted body burdens ................................................................................. 75

A-15 Worker 4 106Ru predicted body burdens ................................................................................. 76

A-16 Worker 4 95Zr/Nb predicted body burdens .............................................................................. 76

A-17 Worker 5 137Cs fit ...................................................................................................................77

A-18 Worker 5 144Ce predicted body burden................................................................................... 77

A-19 Worker 5 106Ru predicted body burden................................................................................... 78

A-20 Worker 5 95

Zr/Nb predicted body burden................................................................................ 79

A-21 Worker 6 137Cs fit ...................................................................................................................80

A-22 Worker 6 144Ce predicted body burden................................................................................... 80

A-23 Worker 6 106Ru predicted body burden................................................................................... 81

A-24 Worker 6 95Zr/Nb predicted body burden................................................................................ 81

A-25 Worker 7 137Cs fit ...................................................................................................................82

A-26 Worker 7 144Ce predicted body burdens ................................................................................. 82

A-27 Worker 7 106Ru predicted body burdens ................................................................................. 83

A-28 Worker 7 95Zr/Nb predicted body burdens .............................................................................. 83

A-29 Worker 8 137Cs fit ...................................................................................................................84

A-30 Worker 8 144Ce predicted body burdens ................................................................................. 85

A-31 Worker 8 106Ru predicted body burdens ................................................................................. 85

A-32 Worker 8 95Zr/Nb predicted body burdens .............................................................................. 86

A-33 Worker 9 137Cs fit ...................................................................................................................87

A-34 Worker 9 144Ce predicted body burdens ................................................................................. 87

A-35 Worker 9 106Ru predicted body burdens ................................................................................. 88

A-36 Worker 9 95Zr/Nb predicted body burdens .............................................................................. 88

A-37 Worker 10 137Cs fit..................................................................................................................89

A-38 Worker 10 144Ce predicted body burdens ............................................................................... 89

A-39 Worker 10 106Ru predicted body burdens ............................................................................... 90

A-40 Worker 10 95Zr/Nb predicted body burdens ............................................................................ 90

A-41 Worker 11 137Cs fit..................................................................................................................91

A-42 Worker 11 144Ce predicted body burdens ............................................................................... 91

A-43 Worker 11 106Ru predicted body burdens ............................................................................... 92

A-44 Worker 11 95Zr/Nb predicted body burdens ............................................................................ 92

A-45 Worker 12 137Cs fit..................................................................................................................93

A-46 Worker 12 144Ce predicted body burdens ............................................................................... 93

A-47 Worker 12 106Ru predicted body burdens ............................................................................... 94
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A-48 Worker 12 95Zr/Nb predicted body burdens ............................................................................ 94

A-49 Worker 13 137Cs fit..................................................................................................................95

A-50 Worker 13 144Ce predicted body burdens ............................................................................... 96

A-51 Worker 13 106Ru predicted body burdens ............................................................................... 96

A-52 Worker 13 95Zr/Nb predicted body burdens ............................................................................ 97

A-53 Worker 14 137Cs fit..................................................................................................................97

A-54 Worker 14 144Ce predicted body burdens ............................................................................... 98

A-55 Worker 14 106Ru predicted body burdens ............................................................................... 99

A-56 Worker 14 95Zr/Nb predicted body burdens ............................................................................ 99
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 8 of 100

ACRONYMS AND ABBREVIATIONS

ATR Advanced Test Reactor

Bq becquerel

cm centimeter

cpm counts per minute

d day

DCF dose conversion factors

DOE U.S. Department of Energy

dpm disintegrations per minute

F fast solubility type

FFTF Fast Flux Test Facility

FP fission products (method)

Ge(Li) lithium-drifted germanium

HPGe hyper-pure germanium

hr hour

IA induced activity (method)

IMBA Integrated Modules for Bioassay Analysis

IRF intake retention fraction

m meter

M moderate solubility type

MDA minimum detectable activity

MFAP mixed fission and activation product

mSv millisievert

MTHM metric tons of heavy metal

MTU metric tons of uranium

MW megawatt

MWd megawatt-day

nCi nanocurie

NIF normalized intake fraction

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities Team

pCi picocurie

S slow solubility type

SRDB Ref ID Site Research Database Reference Identification (number)

SRS Savannah River Site

TRIGA Training, Research, Isotopes, General Atomics

WBC whole-body count

μCi microcurie
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 9 of 100

1.0 INTRODUCTION

ORAUT-OTIB-0054, Fission and Activation Product Assignment for Internal Dose-Related Gross Beta 

and Gross Gamma Analyses (ORAUT 2013; referred to in this report as OTIB-0054), provides a 

method for assigning radionuclide intakes from non-radionuclide-specific radioassays associated with 

mixed fission and activation product (MFAP) source terms from operations involving irradiated nuclear 

fuels. The purpose of this report is threefold:

1. To determine if differences in reactor parameters can have a significant impact on doses 

assigned per OTIB-0054,

2. To use the OTIB-0054 method to develop site-specific intake and activity fraction values for 

assigning MFAP intakes from non-specific (i.e., gross beta and gross gamma) urinalyses 

performed at Savannah River Site (SRS), and

3. To compare doses computed using the SRS-specific intake and activity fraction values with 

doses computed using the guidance given in ORAUT-TKBS-0003, Savannah River Site

(ORAUT 2005), referred to in this report as the SRS Site Profile.

The results of the evaluation performed for item 1 above showed that reactor operating parameters 

different from those in OTIB-0054 could in some cases result in assigned doses that would exceed 

those obtained from OTIB-0054. However, no such combination of reactor parameters and assay 

methods is known to exist at this time. The results in Section 2.0 of this report indicated hypothetical 

increases approaching 30% for doses assigned based on gross gamma assays of raw urine for the 

180-day and 1-year decay times. The results indicated that hypothetical increases in assigned dose 

based on gross beta assays would be small, showing a maximum of 5.2%. In cases where both were 

available, gross beta results would generally be favored over gross gamma due to the greater

sensitivity. The hypothetical increases in assigned doses determined for different reactor parameters 

were primarily the result of higher specific power levels. They were not due to differences in neutron 

spectrum or moderation. 

The conclusion from the evaluation for item 3 above, which were based on the results from item 2, is 

that SRS Site Profile should be revised to incorporate the OTIB-0054 method for assigning fission 

product intakes for both beta and gamma counting. The OTIB-0054 method was developed after the 

guidance in the SRS Site Profile and is considered more rigorous.

Section 2.0 of this report documents comparisons between organ doses computed for the nine 

representative reactor cases considered in OTIB-0054 and doses computed for five cases selected to 

represent production reactor operations at SRS. The purpose of these comparisons was to evaluate 

if differences in reactor parameters could affect the results obtained through application of OTIB-0054. 

The comparisons used intake and activity fraction values derived from fission and activation product 

inventory data for the five SRS-specific cases using the OTIB-0054 method. These comparisons 

were intended only to determine the effect of reactor parameters when using the bioassay 

assumptions from OTIB-0054. They did not include the effects of SRS-specific bioassay methods and 

thus should not be viewed as an evaluation of differences in assigned dose that would be obtained 

using the two sets of reactor data. SRS only performed gross beta or gross gamma counting of 

urinalyses after chemical separation procedures, so the comparisons for other samples (i.e., raw 

urine) are not representative of actual differences. (SRS did count raw urine samples beginning in the 

mid-1960s, but those assays were via gamma spectrometry, not gross gamma counting.) Further, 

differences in radiochemical yields between the separations procedure used at SRS and that 

assumed in OTIB-0054 are not accounted for. Such differences have a trivial effect on gross beta 

counting results (for MFAP source terms) but can result in appreciable differences for gross gamma 

results. However, that must be weighed with the fact gross beta results are the preferred data in 
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 10 of 100

situations when both gross beta and gross gamma assays were performed for a particular type of 

urinalysis, such as the induced activity procedure used at SRS from late 1956 until mid-1966 or so. In 

general, differences in chemical separations procedures are not as important as the difference 

between assays for raw samples versus processed samples (i.e., those subjected to chemical 

separations). That is particularly true for gross beta assays, where the results are dominated by 

radiostrontium, with a minor contribution from barium for short-decayed fuels. 

Section 3.0 of this report expounds upon the SRS-specific activity and intake fraction data derived in 

Section 2.0 to derive activity and intake fraction values that reflect both SRS production reactor 

operations and the specific radiochemistry methods used for gross beta and gross gamma urinalyses

(i.e., the “fission product” and “induced activity” assay methods). Urine activity fraction data are 

provided for three chronic intake periods (90 days, 2 years, and 30 years). 

Section 4.0 of this report documents calculations of committed organ doses for assumed values of 

urinary excretion and intake rate using the SRS-specific intake and activity fraction values derived in 

Section 3.0. The committed organ doses are then compared with those assigned using the default 

guidance provided in the SRS Site Profile (ORAUT 2005, p. 70). 

Because beta urinalysis counting was much more sensitive than gamma urinalysis counting the need 

to calculate intake and dose from a gamma urinalysis result is rare. Therefore, this document focuses 

on beta urinalysis and the default 4,400-dpm/d intake specified in the SRS Site Profile as a means to 

evaluate urinalysis results reported as less than the minimum detectable activity. However, data are 

included to allow interpretation of gross gamma analyses if necessary.

2.0 COMPARISON OF ORGAN DOSES COMPUTED USING THE OTIB-0054 

REPRESENTATIVE REACTOR CASES WITH THOSE COMPUTED FOR THE SRS

PRODUCTION REACTORS

This section documents comparisons between organ doses computed for the nine representative 

reactor cases considered in OTIB-0054 and doses computed for five cases selected to represent 

production reactor operations at SRS. The purpose was to evaluate if differences in reactor 

parameters could affect the results obtained through application of OTIB-0054. These comparisons 

should not be viewed as an evaluation of differences in assigned dose that would be obtained using 

the two sets of reactor data. SRS only performed gross beta or gross gamma counting of urinalyses 

after chemical separation procedures, so the comparisons for other samples are not representative of 

actual differences. Further, differences in radiochemical yields between the separations procedure 

used at SRS versus that assumed in OTIB-0054 are not accounted for. Such differences have a 

trivial effect on gross beta counting results (for MFAP source terms) but can result in appreciable 

differences for gross gamma results. However, that should be weighed with the fact gross beta 

results are the preferred data in situations when both gross beta and gross gamma assays were 

performed for a particular type of urinalysis, such as the induced activity procedure used at SRS from 

late 1956 until mid-1966 or so. In general, differences in chemical separations procedures are not as 

important as the difference between assays for raw samples versus processed samples (i.e., those 

subjected to chemical separations). That is particularly true for gross beta assays, where the results 

are dominated by radiostrontium, with a minor contribution from barium for short-decayed fuels. The 

SRS chemical separations procedures for gross beta and gross gamma urinalyses are considered in 

Section 3.0, which documents the development of SRS-specific activity and intake fraction values for 

assigning dose for non-radionuclide-specific assays for SRS claims.
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2.1 OTIB-0054 METHOD

OTIB-0054 provides a method for deriving intake and activity fraction values for assigning MFAP 

intakes from gross beta or gross gamma radioassay results. The intake and activity fraction values 

were derived from fission and activation product inventory calculations performed using the 

ORIGEN-S code for selected reactors and reactor fuels at predefined decay times (10 days, 40 days, 

180 days, and 1 year). Inventory data were determined across a range of reactor parameters 

(specific power and burnup) for each reactor, as appropriate. Activity fraction values were used to 

convert gross beta or gross gamma results to activity for a given indicator radionuclide (90Sr for gross 

beta counts and 137Cs for gross gamma). The indicator nuclide activity values were then used to 

establish the corresponding intake, which was subsequently used with the intake fraction data to 

assign the intake for the other radionuclides in the mix. 

With respect to urinalysis, the OTIB-0054 method accounts for the following factors:

1. The dosimetrically significant radionuclides in the source term and their intake fractions;

2. The fractions of the significant radionuclides in urine taking into account the body’s biokinetic 

effects on each radionuclide and radioactive decay and progeny ingrowth that occur in a 

sample in the time between collection and counting;

3. The effect of the radiochemistry procedure on the fractions of the radionuclides actually carried 

through to the counting planchet; and

4. The beta and gamma emission rates (i.e., intensities) for each radionuclide.

OTIB-0054 also addresses gross beta or gross gamma assays for air or surface activity. The method 

is the same as that above for urinalysis except the steps accounting for biokinetics and radiochemistry 

are not needed.

Figure 2-1 is a flowchart that shows the relationship these factors have in going from intake to a count 

on a urine sample or vice versa. (The figure specifically references beta counts but the process is 

identical for a gamma count.) The factors are multipliers going from top to bottom or divisors when 

going from bottom to top. In most cases these factors are not known exactly or vary over time and by 

laboratory. 

2.2 REACTORS CONSIDERED IN OTIB-0054 AND IN THIS REPORT

OTIB-0054 considered four reactors representative of reactor sites across the U.S. Department of 

Energy (DOE) complex. The four reactors were the Advanced Test Reactor (ATR), the Fast Flux Test 

Facility (FFTF), the Hanford N Reactor, and a Training, Research, Isotopes, General Atomics (TRIGA) 

reactor (see OTIB-0054 for details). A total of nine ORIGEN-S cases were run to encompass different 

operating conditions with respect to fission and activation product inventory for discharged fuel. The 

nine cases are summarized in Table 2-1. (All tables in this document appear after the References 

section and before Attachment A.)

To evaluate if differences in the reactor parameters considered in the ORIGEN-S runs for OTIB-0054 

could affect assigned doses, three reactor fuels were selected to represent production reactor 

operations at SRS over time. These were:

• The Mark V-B, representing plutonium production in tubular fuels of natural uranium metal;
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 12 of 100

Figure 2-1. Steps and factors in determining beta 

counts in a urine sample from a given intake or in 

determining intake from beta counts.

• The Mark 16, representing plutonium production in mixed lattice cores consisting of oralloyaluminide driver assemblies and depleted uranium targets; and

• The Mark VI-B, representing tritium production in single-assembly driver-target arrangements 

using oralloy aluminide fuel.

Two sets of irradiation parameters were selected for the Mark 16 and Mark VI-B cases. No 

appropriate alternate parameters were identified for the Mark V-B case, so it was run using nominal 

parameters only. The irradiation parameters selected for the five SRS cases are given in Table 2-2.
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 13 of 100

2.3 INTAKE AND ACTIVITY FRACTION DATA FOR THE FIVE SRS CASES 

The OTIB-0054 method was applied to the fission and activation product inventory data for the five 

SRS cases to establish intake and activity fraction values. These values were determined to facilitate 

comparisons with the nine representative reactor cases in OTIB-0054 to evaluate if differences in 

reactor parameters had an effect on assigned intakes. These values do not represent radioassay 

procedures used at SRS and cannot be used for evaluating SRS claims. 

Table 2-3 presents the normalized intake fraction (NIF) values for the dosimetrically significant 

nuclides that were determined from the five SRS cases on the basis of contributing ≥1% to committed 

organ dose. The methods for determining the dosimetrically significant radionuclides and associated 

NIFs for a given set of reactor discharge data are detailed in OTIB-0054. The data specific to the nine 

representative reactor cases are from OTIB-0054.

Table 2-4 presents the NIF values for the simplified source term for the five SRS cases. The 

simplified source term reflects the radionuclides in Table 2-3 that contribute ≥1% to effective dose. 

The NIFs for the simplified source term are the basis for the intake ratio values in Table 2-5. These 

values are used to assign intakes for the associated radionuclides once the indicator radionuclide 

(

90Sr or 137Cs) intake has been established. 

Tables 2-6, 2-7, and 2-8 present the activity fraction values determined for the five SRS cases. The 

fractions in Table 2-6 are used to convert from gross beta or gross gamma urinalysis results to 90Sr or 

137Cs activity, respectively, for samples that have had little or no radiochemical processing before

counting. It is reiterated that these data are included to facilitate comparison with the OTIB-0054 

representative reactor cases and do not represent routine bioassay procedures at SRS. 

The activity fractions in Table 2-7 represent gross beta urinalyses after the radiochemistry procedure 

documented in Section 7.1 of OTIB-0054. This does not represent the procedure used at SRS. 

The activity fractions in Table 2-8 represent gross beta or gross gamma assays for assessments of air 

concentration or surface contamination.

2.4 ORGAN DOSE CALCULATIONS FOR THE REPRESENTATIVE REACTOR AND SRS 

CASES

The activity fraction values for the SRS cases (Tables 2-6, 2-7, and 2-8 of this report) and the 

representative reactor cases (Tables 7-1a, 7-1b, 7-2, and 7-4 of OTIB-0054) were used to calculate 

intakes corresponding to unit assay results for gross beta and gross gamma urinalyses and air 

sample counts.

For the urinalyses, a unit result of 1 pCi/d gross beta or gross gamma was assumed for a 24-hour 

urinalysis after a 1-year chronic intake. For the gross beta analyses, the 90Sr excretion calculated for 

a given reactor case and decay time was converted to intake based on a chronic intake rate of 

4.414 pCi/d of Type F 90Sr, which results in a urinary excretion rate of 1 pCi/d after 1 year. For the 

gross gamma analyses, excretion was converted to intake based on a chronic intake of 2.877 pCi/d of 

Type F 137Cs, which corresponds to an excretion rate of 1 pCi/d at 1 year of chronic intake. The 

intake values for the unit excretion rates were determined using the Integrated Modules for Bioassay 

Analysis (IMBA). 

For air samples, a unit concentration of 1 × 10-10 μCi/cm3 was used to convert from the indicator 

radionuclide activity values to concentration. Intake was then determined by assuming a respiration 

rate of 1.2 m3

/hr for 2,000 hours. 
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 14 of 100

Once the indicator radionuclide intakes were established for each scenario, the corresponding 

associated radionuclide intakes were computed using the intake ratio values in Table 2-5 of this report 

(for the five SRS cases) or Table 7-3 of OTIB-0054 (for the nine representative reactor cases). Organ 

doses were then computed for each scenario and decay interval using dose conversion factors 

(DCFs) determined from IMBA. The DCFs represented dose (in rem) for each radionuclide in the mix 

for a 1-year chronic intake. These values were used to establish dose per unit intake of the indicator 

radionuclide for each reactor case and decay interval for two absorption categories: Most Soluble and 

Least Soluble. The Most Soluble category represented the most soluble absorption type for each 

nuclide in the mix. The Least Soluble category likewise represented the least soluble absorption 

types for each nuclide. Exceptions were that only Type F was used for radiostrontium and only 

Type V (SR-1) for radioiodines.

Per OTIB-0054, the dose assigned for a given assay result should be the maximum obtained across 

the applicable reactor cases and decay times. That guidance was applied to the organ doses 

computed as above for the representative reactor and SRS cases to facilitate comparisons. 

Tables 2-9 through 2-28 show comparisons of the organ dose results for the OTIB-0054 

representative reactor cases and the SRS cases for the following scenarios:

• Gross beta urinalysis for raw urine samples (Tables 2-9 through 2-12),

• Gross beta urinalysis for samples after significant radiochemistry (Tables 2-13 through 2-16),

• Gross gamma urinalysis for raw urine samples (Tables 2-17 through 2-20),

• Gross beta analysis for an air sample (Tables 2-21 through 2-24), and

• Gross gamma analysis for an air sample (Tables 2-25 through 2-28).

In each table, highlights identify instances in which the SRS cases produced a dose that was greater 

than or equal to that from the OTIB-0054 representative reactors.

Note that the 40-day decay time has been included in these dose comparisons for completeness in 

evaluating the effect of different reactor parameters on assigned doses. The 40-day decay time is not 

applicable for assigning doses for SRS claims because separations were not performed on shortdecayed fuels.

2.5 DISCUSSION OF ORGAN DOSE COMPARISONS BETWEEN THE REPRESENTATIVE 

REACTOR AND SRS CASES

The organ dose comparisons for the gross beta urinalyses for the raw urine samples (Tables 2-9 

through 2-12) show that in most cases the representative reactors give doses that are larger than 

those for the SRS cases. Exceptions in which the SRS cases give higher doses are for the thyroid for 

the 10-and 40-day decay times and for four organs at 1 year of decay. The differences in dose for 

these exceptions are not significant. The largest difference is for the thyroid, where the doses from 

the SRS cases exceeded those from the representative reactor cases by 5.2%. Per OTIB-0054, in 

most cases iodine intakes would only be assigned for early years, before the use of ventilation and 

collection systems. For later years it is reasonable to assume that there were no significant intakes 

from iodine at most sites. 

The organ dose comparisons for the gross beta urinalyses after significant radiochemistry 

(Tables 2-13 through 2-16) show that the representative reactors produce significantly larger doses 

than the SRS cases for all organs and decay times. 

For the gross gamma urinalyses (Tables 2-17 through 2-20) the comparisons show numerous 

instances in which the SRS cases gave higher doses than the representative reactor cases. In 

particular, the SRS cases gave higher doses for nearly all of the organs for the 180-day and 1-year 
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 15 of 100

decay times. The differences range from a low of 0.34% to a maximum of 29% (for the adrenals at 

1 year of decay).

The comparisons for the gross beta and gross gamma air samples (Tables 2-21 through 2-28) show 

just three instances where the SRS cases gave larger doses than the representative reactor cases, 

the largest of those being 1.1%. 

3.0 DEVELOPMENT OF SRS-SPECIFIC ACTIVITY FRACTION VALUES FOR ASSIGNING 

MFAP INTAKES FROM GROSS BETA AND GROSS GAMMA URINALYSES

The OTIB-0054 method as described in that document and in Section 2.0 above was used to compute 

activity fraction values applicable to gross beta and gross gamma urinalyses after the fission product

and induced activity procedures described in Section 3.1. Activity fractions were derived for two 

indicator radionuclides for three chronic intake periods. The selected indicator radionuclides were 

90Sr for gross beta analyses and 95Zr for gross gamma. (Cesium-137 could not be used as the 

indicator radionuclide because the SRS radiochemistry procedure did not capture cesium). The three 

chronic intake periods considered were 90 days, 2 years, and 30 years.

Accounting for the site-specific radiochemistry does not affect the determination of the dosimetrically 

significant nuclides or the NIF values from the five SRS cases. Therefore, Tables 2-3, 2-4, and 2-5 of 

this report are unaffected. 

The following subsections focus on urinalyses. For air or other workplace samples at SRS when 

chemical processing was not performed before counting, the activity fraction data in Table 2-8 should 

be used in conjunction with the intake ratio values in Table 2-5 to assign intakes using (1) the 90Sr 

data for gross beta assays and (2) the 137Cs data for gross gamma assays.

3.1 RADIOCHEMISTRY FOR MFAP URINALYSES AT SRS

There were two urinalysis methods at SRS that employed gross beta or gross gamma counting for 

MFAP in urine samples. The first of these was the “fission products” (FP) procedure that appears to 

have come into use in December 1954 (DuPont 1955). The second urinalysis method for MFAP was 

the “induced activity” procedure (IA) that came into use in December 1956 (DuPont 1957, Health

Physics section). The IA procedure, detailed by Boni (1959), employed both gross beta and gross 

gamma counting after an ammoniacal alkaline-earth phosphate precipitation procedure. The specific 

radiochemical method for the FP procedure is not clear but appears to be either similar or indeed 

identical to the IA procedure. The FP assays were only counted for gross beta, so the specifics of the 

radiochemical method are unimportant. Gross beta results for MFAP source terms are dominated by 

radiostrontium activity with a minor contribution from barium for short-decayed fuels. It was 

considered unlikely that a separations procedure for fission products would not have captured 

strontium and barium, even if it did differ from the IA procedure. In a later document, Boni (1963) 

refers to the “mixed fission product analysis” as an ammoniacal alkaline-earth phosphate precipitation 

procedure (i.e., the same procedure he described for the IA procedure in 1959). The FP and IA 

bioassay procedures were differentiated in SRS reports until the combined procedure came into use 

in April 1966, although the only difference could have been the counting methods (gross beta only for 

FP versus gross beta and gross gamma for IA). The gross beta count was the more sensitive of the 

two and would therefore be the primary result for dose assignments.

As of April 1966, a combined fission product and induced activity procedure came into use at SRS 

that involved gamma spectrometry on what appear to be raw urine samples (due to the presence of 

both 40K and 137Cs in the results). The urine activity fractions that are derived in this report for the FP 

and IA analyses are not needed for the combined procedure because it was radionuclide specific. 
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 16 of 100

Some use of the FP and IA methods (FP in particular) are still seen in bioassay data from SRS in 

periods after the gamma spectrometry procedure came into use.

The chemical separation procedure used at SRS did not significantly capture all of the beta-emitting 

radionuclides present in the urine. According to Boni (1959), chemical yields for some of the common 

fission products were measured as follows: 60Co 85%, 59Fe 98%, 65Zn 95%, 51Cr 90%, 89Sr 92%, 90Sr 

103%, 103Ru 40% to 50%, 144Ce 101%, and Zr/Nb 95%. This analysis assumed that the SRS 

procedure also quantitatively captured promethium, europium, praseodymium, and neodymium (the 

Boni paper states that rare earths are captured) as well as barium, lanthanum, and yttrium (though it 

does not appear SRS tested for these directly). It was also assumed that cesium, iodine, tellurium,

and molybdenum were not captured because of the similarities between the SRS and Hanford 

procedures. Because chemical yields vary by batch, and consistent with the OTIB-0054 approach, 

the fractional chemical yields in this report were rounded to 1 or 0. These yields are shown in 

Table 3-1 for the complete list of dosimetrically significant radionuclides for the five SRS cases (i.e., 

those in Table 2-3). The yields for ruthenium have been set to zero in Table 3-1 because ruthenium

was volatilized in the muffling step of the Boni procedure and was therefore not present when 

samples were counted [DuPont 1957, p. 228]. 

3.2 CALCULATION OF THE SRS-SPECIFIC ACTIVITY FRACTIONS FOR GROSS BETA 

AND GROSS GAMMA URINALYSES

Activity fractions for 90Sr and 95Zr were calculated per Section 7.1 of OTIB-0054 using the chemical 

yield values in Table 3-1 in conjunction with the appropriate beta and gamma emission yields and the 

intake retention fraction (IRF) values in Table 3-2. Emission yields and IRFs are only shown for the 

radionuclides carried through by the SRS radiochemistry procedure. Per the OTIB-0054 method, 

indicator radionuclide activity fraction values were computed using only the least soluble absorption 

type for the associated radionuclides in the mix. The SRS-specific 90Sr (gross beta) and 95Zr (gross 

gamma) activity fraction values are in Tables 3-3 and 3-4, respectively.

The activity fraction values in Tables 3-3 and 3-4 were used to determine the indicator radionuclide 

activity associated with a given counting result. The indicator radionuclide excretion values were then 

used to establish the corresponding intake. Next, intake ratio tables were used to compute the intake 

for the additional associated radionuclides. For 90Sr, the applicable intake ratio values are given in 

Table 2-5. Intake ratios for 95Zr (to be used for SRS-specific gross gamma urinalyses) are given in 

Table 3-5. 

4.0 COMMITTED ORGAN DOSES COMPUTED USING THE SRS-SPECIFIC ACTIVITY AND 

INTAKE FRACTION VALUES

In Section 4.1 below the SRS-specific gross beta urine activity fractions developed in Section 3.2 

were used in conjunction with the SRS-specific associated radionuclide intake ratios discussed in 

Section 2.3 to compute committed organ doses for a unit gross beta urinalysis result. Organ doses 

were computed for both 90-day and 30-year intake periods.

Section 4.2 describes use of the SRS-specific NIF values discussed in Section 2.3 to apportion an 

intake of 4,400 dpm/d, which is the recommended intake to assign for missed dose calculations per 

the SRS site profile. The apportioned intake was used to compute committed organ doses for intake 

periods of 90 days and 30 years.
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 17 of 100

4.1 COMMITTED ORGAN DOSES FOR A UNIT URINARY EXCRETION RATE OF 1 

BECQUEREL PER DAY

The SRS-specific 90Sr activity fractions (Table 3-3) for the 90-day and 30-year intake periods were 

used to compute the 90Sr activity corresponding to a gross beta assay result of 1 Bq/d for a 24-hour 

urinalysis for each of the five SRS cases for the 10-day, 180-day, and 1-year decay times. SRS 

seldom dissolved short-cooled fuel (Kantelo et al. 1993, p. 26). Therefore, these evaluations only 

considered fuel cooled or decayed 10 days, 180 days, or 1 year, as discussed in OTIB-0054. In 

general, these categories apply to reactor workers (10-day-decayed fuel mixtures), dissolution 

facilities (180-day-decayed fuel mixtures) and waste management facilities (1-year-decayed fuel 

mixtures). 

The 90Sr activity (excretion) results were converted to chronic intake rate using factors of 4.691 Bq/d 

for the 90-day intake period and 4.017 Bq/d for the 30-year period. These are values from IMBA 

version 4.0.9 for chronic intake of Type F 90Sr for a urinary excretion of 1 Bq/d. The intakes of the 

associated radionuclides were determined from the 90Sr intakes using the ratios in Table 2-5. 

Committed organ doses (two sets, one for each intake period) were then computed using DCFs (in 

mSv/Bq) from RadToolbox Version 2.0.0 for the most soluble and least soluble absorption types.

Tables 4-1 through 4-3 show the computed committed organ doses (in mSv) for each decay time for 

the two intake periods. Per the OTIB-0054 method, the maximum value determined for a given organ 

was assigned for each intake period. 

4.2 COMMITTED ORGAN DOSES FOR AN INTAKE RATE OF 4,400 DPM PER DAY

The SRS Site Profile recommends assigning an intake of 4,400 dpm/d for missed dose calculations 

for mixed fission products (ORAUT 2005, p. 82). Tables 4.4.2-6 and 4.4.2-7 of that document provide 

guidance on how to apportion the 4,400 dpm/d among radionuclides and absorption types. 

Table 4.4.2-6 can be used for upper bound doses and Table 4.4.2-7 can be used for more realistic 

assessments. Committed organ doses were compared using the intake radionuclide ratios from 

OTIB-0054 with doses using the guidance in Table 4.4.2-7.

The SRS-specific NIF values in Table 2-4 were used to apportion an intake of 4,400 dpm (73.3 Bq) to 

determine the fraction due to 90Sr. However, because the 4,400 dpm/d intake specified by the SRS 

Site Profile represents particulate activity only, the Table 2-4 values were renormalized with the 131I 

components removed. These modified (particulate-only) NIF values (Table 4-4) were then used to 

compute the 90Sr component of the 4,400 dpm/d intake rate for each reactor case for the 10-day, 180-

day, and 1-year decay times. The intake rates were then converted to total intake by multiplying by 

periods of 90 days and 30 years (10,957 days).

The 90Sr intakes that correspond to the 4,400 dpm/d intake rate were used in conjunction with 

Table 2-5 to determine the associated radionuclide intakes for each reactor and decay time for the 

90-day and 30-year periods. Note that these values include the 131I components. The resulting intake 

values were then used to compute committed organ doses using DCFs from RadToolbox. The organ 

doses were computed for the most soluble and least soluble absorption types and the maximum for 

each organ was selected for the two intake periods.

Tables 4-5 through 4-7 show comparisons of the maximum committed doses determined for each 

organ from the 4,400-dpm/d intake rate for the two intake periods and each of the 10-day, 180-day, 

and 1-year decay times.
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 18 of 100

5.0 COMPARISON OF DOSES ASSIGNED USING THE SRS-SPECIFIC INTAKE AND 

ACTIVITY FRACTION VALUES WITH THOSE ASSIGNED PER THE SRS SITE 

PROFILE

The SRS Site Profile recommends that fission product urinalysis results be interpreted as follows 

(ORAUT 2005, p. 70):

1. 100% Type F 90Sr if the disease is related to bone or bone marrow plus an equal intake of 

137Cs (Type F) and a 3-fold intake of 106Ru (Type F). This assumption should be used for other 

disease locations that are not specifically mentioned in the next two bullets.

2. 100% Type M 144Ce if the disease is related to the liver plus an equal intake of 106Ru (Type F) 

and a 20% intake of 137Cs (Type F)

3. 100% Type M 144Ce if the disease is related to the respiratory tract or digestive tract plus an 

equal intake of Type S 106Ru and a 20% intake of 137Cs (Type F)

Tables 5-1 through 5-3 show comparisons of committed organ doses computed using the Site Profile 

assumptions with those determined using the SRS-specific intake and activity fraction values for a 

1-Bq/d unit excretion rate. Comparisons are given for the 10-day, 180-day, and 1-year decay times 

for the 90-day and 30-year intake periods.

Tables 5-4 through 5-6 show comparisons of committed organ doses computed using the Site Profile 

assumptions with those determined using the SRS-specific intake and activity fraction values for a 

chronic intake rate of 4,400 dpm/d. Comparisons are given for the 10-day, 180-day, and 1-year decay 

times for the 90-day and 30-year intake periods. 

6.0 CONCLUSIONS AND RECOMMENDATIONS

6.1 COMPARISONS OF THE REPRESENTATIVE REACTOR AND SRS CASES

The comparisons between organ doses computed using the activity and intake fraction values for the 

nine representative reactor cases considered in OTIB-0054 with those computed using activity and 

intake fraction values for cases selected to represent production reactor operations at SRS showed 

that the representative reactor doses exceeded those from the SRS cases in most cases, with the 

notable exception of the gross gamma results for the 180-day and 1-year decay times. The maximum 

amount by which dose from the SRS values exceeded that from the representative reactors was 

28.9%. This occurred for the adrenals at 1 year of decay for a gross gamma urinalysis. That result 

represents a gross gamma count on a raw urine sample, a type of analysis not known to have been 

used at SRS. Therefore, it does not represent a nonfavorable bias between doses assigned via 

OTIB-0054 and those assigned using the SRS-specific values in this report. However, it does show 

that differences in reactor parameters from those in OTIB-0054 can, hypothetically, result in higher 

assigned doses, although in general gross gamma results would only be used if there was no 

corresponding gross beta result for a given assay.

6.2 COMPARISON BASED ON BETA ACTIVITY IN URINE

For all organs except the thyroid, the SRS Site Profile guidance resulted in overestimated doses in 

comparison with those from the SRS-specific intake and activity fraction values that were established 

using the OTIB-0054 method for all absorption types and fuel decay periods and over a very broad 

range of intake periods. The overestimates ranged from 2 to 5 orders of magnitude for all organs and 

decay times except for the thyroid at 10 days decay. For the thyroid for reactor workers (10-daydecayed fuel), the SRS Site Profile guidance underestimated the dose by approximately 1 order of 
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 19 of 100

magnitude for the 90-day intake period because 131I represents such a large component of the total 

activity at short decay times.

6.3 COMPARISON BASED ON INTAKES

For all organs except the thyroid, the SRS Site Profile guidance in Table 4.4.2-7 resulted in 

overestimated doses in comparison with those from the OTIB-0054 method for all absorption types, 

fuel decay periods, and a broad range of intake periods. The overestimates ranged from 3% to more 

than a factor of 20 for all organs and decay times except for the thyroid at 10 days decay. For the 

thyroid, for 10-day-decayed fuel contamination only, the Table 4.4.2-7 guidance underestimated the 

dose by more than 3 orders of magnitude because of the large impact of the 131I.

6.4 COMPARISON TO TEST CASE WHOLE BODY COUNTS

The method for calculating the ratios of the fission products in relation to the indicator radionuclides 

introduces considerable conservatism. To evaluate whether the ratios are reasonable, the body 

burdens that would be predicted by using these ratios were compared to actual values. Attachment A 

contains an evaluation of 14 test cases for individuals with positive 137Cs whole-body count (WBC) 

results. The positive results for these individuals were used to calculate intakes in accordance with 

normal dose reconstruction methods. Intakes of associated fission products were then calculated,

and predicted body burdens of these radionuclides were modeled for 106Ru, 95Zr/Nb, and 144Ce, three 

radionuclides detectable by WBCs. The predicted body burdens were generally consistent with the 

WBC results.

7.0 RECOMMENDATION

The SRS Site Profile guidance was developed before OTIB-0054. The latter is considered more 

accurate, and it is used for other sites. The SRS Site Profile should be revised to incorporate the 

OTIB-0054 method for assigning MFAP intakes from gross beta and gross gamma counting results 

(i.e. the fission product and induced activity procedures). This may result in the need for upward 

revision of assigned thyroid doses in some cases. In cases where both gross beta and gross gamma 

results are available for a given sample the gross beta results should be used by default since that 

was the more sensitive of the two methods. Table 3-3 of this report would be used to assign the 90Sr 

intake associated with a given gross beta urinalysis result. If the gross gamma result was selected 

then Table 3-4 would be used to assign the 95Zr intake. Intakes for the other radionuclides in the mix 

would then be assigned using Table 2-5 for the 90Sr indicator (i.e. gross beta) or Table 3-5 for 95Zr (i.e. 

gross gamma).
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 20 of 100

REFERENCES

Boni, A. L., 1959, Rapid Determination of Mixed Beta-Gamma Radionuclides in Urine, DPSPU-58-

030-011, E. I. DuPont de Nemours and Company, Savannah River Plant, Aiken, South 

Carolina. [SRDB Ref ID: 49225]

Boni, A. L., 1963, Urinary Excretion of Sr-90 Following an Inhalation Assimilation, DPSPU-63-11-2,

E. I. DuPont de Nemours and Company, Savannah River Plant, Aiken, South Carolina, 

February. [SRDB Ref ID: 49236]

DuPont (E. I. du Pont de Nemours and Company), undated, Evaluation of a Whole Body Count, 

DPSOL 47-614, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 32168]

DuPont (E. I. du Pont de Nemours and Company), 1955, Health Physics Monthly Report, December 

1954, Savannah River Plant, Aiken, South Carolina. [SRDB Ref ID: 56524, p. 2]

DuPont (E. I. du Pont de Nemours and Company), 1957, Monthly Progress Report, December 1956, 

Works Technical Department, DPSP 56-1-12, Savannah River Plant, Aiken, South Carolina, 

January 18. [SRDB Ref ID: 11573]

Kantelo, M. V., L. R. Bauer, W. L. Marter, C. E. Murphy, Jr., and C. C. Zeigler, 1993, Radioiodine in 

the Savannah River Site Environment, WSRC-RP-90-424-2, Westinghouse Savannah River 

Company, Savannah River Site, Aiken, South Carolina, January 15. [SRDB Ref ID: 46150]

ORAUT (Oak Ridge Associated Universities Team), 2005, Savannah River Site, ORAUT-TKBS-0003, 

Rev. 03, Oak Ridge, Tennessee, April 5.

ORAUT (Oak Ridge Associated Universities Team), 2013, Fission and Activation Product Assignment 

for Internal Dose-Related Gross Beta and Gross Gamma Analyses, ORAUT-OTIB-0054, Rev. 

01, Oak Ridge, Tennessee, June 13.

Watts, J. R., 1962–1967, “Health Physics Methods,” logbook covering August 30, 1962, to October 

26, 1967, E. I. du Pont de Nemours and Company, Savannah River Plant, Aiken, South 

Carolina. [SRDB Ref ID: 61711]
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 21 of 100

Table 2-1. ORIGEN-S irradiation parameters for the nine representative reactor cases.

Case Parameters Basis

ATR 1 Specific power = 2379.1 MW/MTU

Irradiation time = 132.27 days

Burnup = 314,684 MWd/MTU

Maximum burnup at nominal power.

ATR 2 Specific power = 8651.2 MW/MTU

Irradiation time = 36.4 days

Burnup =314,904 MWd/MTU

Maximum burnup at maximum assembly power.

ATR 3 Specific power = 2379.1 MW/MTU

Irradiation time = 56 days

Burnup = 133,230 MWd/MTU

Nominal burnup at nominal power.

FFTF 1 Specific power = 163.8 MW/MTHM

Irradiation time = 929.4 days

Burnup = 152,230 MWd/MTHM

Maximum burnup at nominal power.

FFTF 2 Specific power = 163.8 MW/MTHM

Irradiation time = 488.3 days

Burnup = 79,984 MWd/MTHM

Nominal burnup at nominal power.

N Reactor 1 Specific power = 10.4 MW/MTU

Irradiation time = 114.2 days

Burnup = 1188 MWd/MTU

Production of weapons-grade plutonium (nominal 6% 240Pu content) at nominal power.

N Reactor 2 Specific power = 10.4 MW/MTU

Irradiation time = 285.6 days

Burnup = 2970 MWd/MTU

Production of fuel-grade plutonium (nominal 12% 240Pu 

content) at nominal power.

TRIGA 1 Specific power = 15.57 MWd/MTU

Irradiation time = 730.1 days

Burnup = 11,368 MWd/MTU

Maximum burnup at nominal power.

TRIGA 2 Specific power = 15.57 MW/MTU

Irradiation time = 115.2 days

Burnup = 1994 MWd/MTU

Nominal burnup at nominal power.

Table 2-2. ORIGEN-S irradiation parameters for the five SRS cases.

Case Parameters Basis

Mark V-B Specific power = 25.5 MW/MTU

Irradiation time = 43.14 days

Burnup = 1,100 MWd/MTU

Production of weapons-grade plutonium (nominal 6% 240Pu content) at nominal power.

Mark 16 1 Specific power = 896.08 MW/MTU

Irradiation time = 240 days

Burnup = 215,059 MWd/MTU

Typical Mark 16/31 core irradiated for four sub-cycles 

of 60 days each, representing the high burnup case.

Mark 16 2 Specific power = 896.08 MW/MTU

Irradiation time = 160 days

Burnup = 143,373 MWd/MTU

Typical Mark 16/31 core irradiated for four sub-cycles 

of 40 days each, representing the low burnup case. 

Mark VI-B 1 Specific power = 1392.9 MW/MTU

Irradiation time = 182 days

Burnup = 253,508 MWd/MTU

Maximum assembly power for a typical cycle duration.

Mark VI-B 2 Specific power = 1160.32 MW/MTU

Irradiation time = 182 days

Burnup = 211,178 MWd/MTU

Nominal assembly power for a typical cycle duration.
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 22 of 100

Table 2-3. Normalized intake fractions for the dosimetrically important radionuclides.

Radionuclide

Mk V-B 1 Mk 16 1 Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 1.40E-02 6.79E-02 6.83E-02 1.69E-02 2.95E-02 8.30E-02 4.98E-02 9.71E-03 2.80E-02 8.60E-02 5.73E-02 1.21E-02

Sr-90 1.28E-04 9.35E-04 6.36E-03 1.96E-02 6.94E-04 2.94E-03 1.19E-02 2.90E-02 4.74E-04 2.20E-03 9.88E-03 2.61E-02

Y-90 1.28E-04 9.35E-04 6.36E-03 1.96E-02 6.97E-04 2.94E-03 1.19E-02 2.90E-02 4.76E-04 2.20E-03 9.88E-03 2.61E-02

Y-91 1.62E-02 8.28E-02 1.08E-01 3.77E-02 3.65E-02 1.09E-01 8.48E-02 2.33E-02 3.39E-02 1.10E-01 9.51E-02 2.85E-02

Zr-95 1.77E-02 9.34E-02 1.41E-01 5.92E-02 4.04E-02 1.24E-01 1.12E-01 3.71E-02 3.68E-02 1.24E-01 1.23E-01 4.45E-02

Nb-95 9.03E-03 8.51E-02 2.58E-01 1.26E-01 4.16E-02 1.62E-01 2.17E-01 7.99E-02 3.40E-02 1.52E-01 2.37E-01 9.56E-02

Mo-99 4.19E-03 1.58E-05 4.94E-20 8.20E-40 3.55E-03 7.79E-06 1.45E-20 1.90E-40 3.72E-03 8.90E-06 1.84E-20 2.62E-40

Ru-103 1.42E-02 6.11E-02 3.54E-02 4.21E-03 1.92E-02 4.81E-02 1.66E-02 1.56E-03 1.86E-02 5.07E-02 1.94E-02 1.98E-03

Ru-106 6.28E-04 4.34E-03 2.29E-02 5.07E-02 1.20E-03 4.83E-03 1.52E-02 2.66E-02 8.39E-04 3.68E-03 1.29E-02 2.44E-02

Te-129m 4.99E-04 1.97E-03 7.52E-04 5.16E-05 6.12E-04 1.40E-03 3.19E-04 1.73E-05 6.01E-04 1.50E-03 3.79E-04 2.24E-05

Te-132 4.58E-03 5.65E-05 4.50E-17 1.13E-33 3.73E-03 2.68E-05 1.27E-17 2.52E-34 3.89E-03 3.05E-05 1.61E-17 3.46E-34

I-131 5.55E-01 3.05E-01 1.20E-05 4.44E-12 4.63E-01 1.48E-01 3.48E-06 1.01E-12 4.78E-01 1.67E-01 4.34E-06 1.38E-12

I-132 2.36E-01 2.91E-03 2.32E-15 5.83E-32 1.92E-01 1.38E-03 6.55E-16 1.30E-32 2.00E-01 1.57E-03 8.27E-16 1.78E-32

Cs-134 1.33E-05 9.44E-05 5.70E-04 1.50E-03 6.50E-04 2.69E-03 9.67E-03 2.01E-02 2.68E-04 1.21E-03 4.83E-03 1.09E-02

Cs-137 1.44E-04 1.05E-03 7.16E-03 2.21E-02 7.05E-04 2.99E-03 1.21E-02 2.95E-02 4.81E-04 2.23E-03 1.00E-02 2.65E-02

Ba-140 2.71E-02 3.87E-02 1.32E-04 1.76E-08 2.67E-02 2.22E-02 4.50E-05 4.75E-09 2.76E-02 2.50E-02 5.62E-05 6.45E-09

La-140 3.11E-02 4.46E-02 1.52E-04 2.03E-08 3.07E-02 2.56E-02 5.18E-05 5.47E-09 3.16E-02 2.88E-02 6.48E-05 7.43E-09

Ce-141 2.37E-02 9.12E-02 3.16E-02 1.91E-03 3.49E-02 7.82E-02 1.62E-02 7.70E-04 3.49E-02 8.54E-02 1.96E-02 1.01E-03

Ce-144 4.34E-03 2.94E-02 1.44E-01 2.86E-01 1.78E-02 7.04E-02 2.05E-01 3.22E-01 1.33E-02 5.73E-02 1.85E-01 3.16E-01

Pr-143 2.82E-02 4.46E-02 2.40E-04 5.90E-08 2.80E-02 2.57E-02 8.25E-05 1.60E-08 2.90E-02 2.91E-02 1.04E-04 2.18E-08

Pr-144 4.34E-03 2.94E-02 1.44E-01 2.86E-01 1.78E-02 7.04E-02 2.05E-01 3.22E-01 1.33E-02 5.73E-02 1.85E-01 3.16E-01

Nd-147 9.13E-03 1.00E-02 1.00E-05 2.64E-10 8.39E-03 5.37E-03 3.19E-06 6.65E-11 8.78E-03 6.13E-03 4.03E-06 9.15E-11

Pm-147 4.52E-04 3.88E-03 2.48E-02 6.76E-02 1.95E-03 8.46E-03 3.15E-02 6.79E-02 1.50E-03 7.22E-03 2.99E-02 7.00E-02

Eu-154 7.70E-07 5.59E-06 3.72E-05 1.11E-04 2.05E-05 8.64E-05 3.43E-04 8.11E-04 8.43E-06 3.89E-05 1.71E-04 4.39E-04

Eu-155 4.25E-06 3.07E-05 1.99E-04 5.76E-04 1.15E-05 4.81E-05 1.86E-04 4.25E-04 5.80E-06 2.66E-05 1.14E-04 2.83E-04
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 23 of 100

Radionuclide

Mk VI-B 1 Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 2.87E-02 8.55E-02 5.51E-02 1.14E-02 2.86E-02 8.55E-02 5.51E-02 1.14E-02

Sr-90 5.35E-04 2.40E-03 1.05E-02 2.70E-02 5.34E-04 2.40E-03 1.05E-02 2.70E-02

Y-90 5.37E-04 2.41E-03 1.05E-02 2.70E-02 5.35E-04 2.40E-03 1.05E-02 2.70E-02

Y-91 3.50E-02 1.10E-01 9.22E-02 2.69E-02 3.49E-02 1.10E-01 9.23E-02 2.69E-02

Zr-95 3.82E-02 1.24E-01 1.20E-01 4.22E-02 3.81E-02 1.24E-01 1.20E-01 4.23E-02

Nb-95 3.67E-02 1.56E-01 2.32E-01 9.09E-02 3.66E-02 1.56E-01 2.32E-01 9.09E-02

Mo-99 3.67E-03 8.53E-06 1.70E-20 2.37E-40 3.68E-03 8.56E-06 1.71E-20 2.38E-40

Ru-103 1.87E-02 4.96E-02 1.84E-02 1.83E-03 1.86E-02 4.95E-02 1.84E-02 1.83E-03

Ru-106 9.13E-04 3.89E-03 1.31E-02 2.43E-02 9.02E-04 3.85E-03 1.30E-02 2.41E-02

Te-129m 6.02E-04 1.46E-03 3.56E-04 2.05E-05 5.99E-04 1.45E-03 3.56E-04 2.05E-05

Te-132 3.84E-03 2.92E-05 1.49E-17 3.13E-34 3.85E-03 2.93E-05 1.49E-17 3.15E-34

I-131 4.72E-01 1.60E-01 4.03E-06 1.25E-12 4.72E-01 1.60E-01 4.03E-06 1.25E-12

I-132 1.98E-01 1.50E-03 7.66E-16 1.61E-32 1.98E-01 1.51E-03 7.69E-16 1.62E-32

Cs-134 4.44E-04 1.94E-03 7.51E-03 1.65E-02 3.59E-04 1.57E-03 6.08E-03 1.34E-02

Cs-137 5.42E-04 2.43E-03 1.06E-02 2.73E-02 5.40E-04 2.43E-03 1.06E-02 2.73E-02

Ba-140 2.73E-02 2.41E-02 5.23E-05 5.86E-09 2.73E-02 2.41E-02 5.24E-05 5.87E-09

La-140 3.14E-02 2.77E-02 6.02E-05 6.74E-09 3.14E-02 2.77E-02 6.03E-05 6.76E-09

Ce-141 3.50E-02 8.32E-02 1.84E-02 9.32E-04 3.50E-02 8.33E-02 1.85E-02 9.34E-04

Ce-144 1.46E-02 6.12E-02 1.91E-01 3.19E-01 1.46E-02 6.12E-02 1.91E-01 3.19E-01

Pr-143 2.87E-02 2.80E-02 9.62E-05 1.98E-08 2.88E-02 2.81E-02 9.67E-05 1.99E-08

Pr-144 1.46E-02 6.12E-02 1.91E-01 3.19E-01 1.46E-02 6.12E-02 1.91E-01 3.19E-01

Nd-147 8.67E-03 5.87E-03 3.74E-06 8.28E-11 8.76E-03 5.94E-03 3.79E-06 8.38E-11

Pm-147 1.54E-03 7.15E-03 2.87E-02 6.55E-02 1.62E-03 7.52E-03 3.02E-02 6.89E-02

Eu-154 1.37E-05 6.11E-05 2.60E-04 6.53E-04 1.09E-05 4.89E-05 2.08E-04 5.23E-04

Eu-155 7.37E-06 3.28E-05 1.36E-04 3.30E-04 6.65E-06 2.96E-05 1.23E-04 2.98E-04
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 24 of 100

Table 2-4. Normalized intake fractions for the reduced list of dosimetrically important radionuclides.

Radionuclide

Mk V-B base Mk 16 base Mk 16 A1

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 2.05E-02 7.79E-02 8.05E-02 2.43E-02 4.11E-02 9.53E-02 6.37E-02 1.50E-02 3.94E-02 9.81E-02 7.12E-02 1.84E-02

Sr-90 1.88E-04 1.07E-03 7.49E-03 2.82E-02 9.69E-04 3.38E-03 1.53E-02 4.48E-02 6.68E-04 2.50E-03 1.23E-02 3.97E-02

Y-91 2.37E-02 9.51E-02 1.28E-01 5.44E-02 5.10E-02 1.25E-01 1.08E-01 3.60E-02 4.77E-02 1.26E-01 1.18E-01 4.33E-02

Zr-95 2.59E-02 1.07E-01 1.66E-01 8.54E-02 5.64E-02 1.43E-01 1.43E-01 5.73E-02 5.19E-02 1.41E-01 1.53E-01 6.77E-02

Nb-95 1.32E-02 9.77E-02 3.04E-01 1.82E-01 5.80E-02 1.86E-01 2.78E-01 1.23E-01 4.80E-02 1.73E-01 2.95E-01 1.45E-01

Ru-103 2.08E-02 7.01E-02 4.17E-02 6.07E-03 2.68E-02 5.52E-02 2.12E-02 2.41E-03 2.62E-02 5.78E-02 2.42E-02 3.02E-03

Ru-106 9.19E-04 4.98E-03 2.70E-02 7.30E-02 1.68E-03 5.55E-03 1.95E-02 4.10E-02 1.18E-03 4.20E-03 1.60E-02 3.71E-02

I-131 8.12E-01 3.50E-01 1.41E-05 6.39E-12 6.47E-01 1.70E-01 4.44E-06 1.57E-12 6.73E-01 1.90E-01 5.39E-06 2.09E-12

Cs-134 1.94E-05 1.08E-04 6.71E-04 2.16E-03 9.08E-04 3.09E-03 1.24E-02 3.10E-02 3.78E-04 1.38E-03 6.00E-03 1.66E-02

Cs-137 2.11E-04 1.21E-03 8.43E-03 3.18E-02 9.85E-04 3.44E-03 1.55E-02 4.56E-02 6.77E-04 2.54E-03 1.24E-02 4.03E-02

Ce-141 3.46E-02 1.05E-01 3.73E-02 2.75E-03 4.87E-02 8.98E-02 2.07E-02 1.19E-03 4.92E-02 9.74E-02 2.43E-02 1.54E-03

Ce-144 6.34E-03 3.38E-02 1.69E-01 4.12E-01 2.49E-02 8.09E-02 2.62E-01 4.97E-01 1.87E-02 6.54E-02 2.30E-01 4.80E-01

Pr-143 4.13E-02 5.12E-02 2.83E-04 8.50E-08 3.91E-02 2.95E-02 1.05E-04 2.47E-08 4.09E-02 3.32E-02 1.29E-04 3.32E-08

Pm-147 6.62E-04 4.45E-03 2.92E-02 9.74E-02 2.73E-03 9.71E-03 4.03E-02 1.05E-01 2.12E-03 8.23E-03 3.72E-02 1.06E-01

Radionuclide

Mk VI-B base Mk VI-B A1

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 4.03E-02 9.77E-02 6.91E-02 1.74E-02 4.03E-02 9.77E-02 6.91E-02 1.74E-02

Sr-90 7.52E-04 2.75E-03 1.31E-02 4.13E-02 7.51E-04 2.74E-03 1.31E-02 4.13E-02

Y-91 4.91E-02 1.26E-01 1.16E-01 4.12E-02 4.91E-02 1.26E-01 1.16E-01 4.12E-02

Zr-95 5.37E-02 1.42E-01 1.50E-01 6.46E-02 5.36E-02 1.42E-01 1.50E-01 6.47E-02

Nb-95 5.16E-02 1.78E-01 2.91E-01 1.39E-01 5.15E-02 1.78E-01 2.91E-01 1.39E-01

Ru-103 2.63E-02 5.66E-02 2.31E-02 2.80E-03 2.62E-02 5.65E-02 2.30E-02 2.80E-03

Ru-106 1.28E-03 4.44E-03 1.65E-02 3.72E-02 1.27E-03 4.39E-03 1.63E-02 3.68E-02

I-131 6.63E-01 1.83E-01 5.05E-06 1.91E-12 6.63E-01 1.83E-01 5.06E-06 1.91E-12

Cs-134 6.24E-04 2.22E-03 9.42E-03 2.53E-02 5.05E-04 1.80E-03 7.63E-03 2.05E-02

Cs-137 7.61E-04 2.78E-03 1.33E-02 4.19E-02 7.59E-04 2.77E-03 1.33E-02 4.18E-02

Ce-141 4.92E-02 9.50E-02 2.31E-02 1.43E-03 4.93E-02 9.51E-02 2.32E-02 1.43E-03

Ce-144 2.06E-02 6.99E-02 2.40E-01 4.87E-01 2.05E-02 6.98E-02 2.40E-01 4.87E-01

Pr-143 4.04E-02 3.19E-02 1.21E-04 3.03E-08 4.05E-02 3.21E-02 1.21E-04 3.04E-08

Pm-147 2.16E-03 8.17E-03 3.59E-02 1.00E-01 2.28E-03 8.59E-03 3.78E-02 1.05E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 25 of 100

Table 2-5. Associated radionuclide activity fractions for assigning intakes relative to 90Sr or 137Cs.

Table 2-5 values: Mark V-B

Nuclide

Intake relative to Sr-90

Nuclide

Intake relative to Cs-137

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 1.09E+02 7.26E+01 1.07E+01 8.61E-01 Sr-89 9.72E+01 6.45E+01 9.55E+00 7.64E-01

Sr-90 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Sr-90 8.89E-01 8.89E-01 8.88E-01 8.88E-01

Y-91 1.26E+02 8.86E+01 1.70E+01 1.93E+00 Y-91 1.12E+02 7.88E+01 1.51E+01 1.71E+00

Zr-95 1.38E+02 9.98E+01 2.21E+01 3.02E+00 Zr-95 1.23E+02 8.88E+01 1.97E+01 2.69E+00

Nb-95 7.05E+01 9.10E+01 4.06E+01 6.45E+00 Nb-95 6.27E+01 8.09E+01 3.61E+01 5.73E+00

Ru-103 1.11E+02 6.53E+01 5.57E+00 2.15E-01 Ru-103 9.84E+01 5.81E+01 4.95E+00 1.91E-01

Ru-106 4.90E+00 4.64E+00 3.61E+00 2.59E+00 Ru-106 4.35E+00 4.12E+00 3.20E+00 2.30E+00

I-131 4.33E+03 3.27E+02 1.89E-03 2.26E-10 I-131 3.85E+03 2.90E+02 1.68E-03 2.01E-10

Cs-134 1.04E-01 1.01E-01 8.96E-02 7.65E-02 Cs-134 9.21E-02 8.98E-02 7.96E-02 6.79E-02

Cs-137 1.12E+00 1.12E+00 1.13E+00 1.13E+00 Cs-137 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Ce-141 1.85E+02 9.76E+01 4.97E+00 9.74E-02 Ce-141 1.64E+02 8.67E+01 4.42E+00 8.65E-02

Ce-144 3.38E+01 3.15E+01 2.26E+01 1.46E+01 Ce-144 3.01E+01 2.80E+01 2.01E+01 1.30E+01

Pr-143 2.20E+02 4.77E+01 3.78E-02 3.01E-06 Pr-143 1.96E+02 4.24E+01 3.36E-02 2.67E-06

Pm-147 3.53E+00 4.15E+00 3.90E+00 3.45E+00 Pm-147 3.14E+00 3.69E+00 3.46E+00 3.06E+00

Table 2-5 values: Mark 16 1

Nuclide

Intake relative to Sr-90

Nuclide

Intake relative to Cs-137

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 4.25E+01 2.82E+01 4.17E+00 3.34E-01 Sr-89 4.18E+01 2.77E+01 4.11E+00 3.29E-01

Sr-90 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Sr-90 9.84E-01 9.84E-01 9.83E-01 9.83E-01

Y-91 5.26E+01 3.70E+01 7.11E+00 8.04E-01 Y-91 5.18E+01 3.64E+01 6.99E+00 7.90E-01

Zr-95 5.82E+01 4.22E+01 9.35E+00 1.28E+00 Zr-95 5.73E+01 4.15E+01 9.20E+00 1.26E+00

Nb-95 5.99E+01 5.51E+01 1.82E+01 2.75E+00 Nb-95 5.89E+01 5.42E+01 1.79E+01 2.70E+00

Ru-103 2.77E+01 1.63E+01 1.39E+00 5.37E-02 Ru-103 2.72E+01 1.61E+01 1.37E+00 5.28E-02

Ru-106 1.73E+00 1.64E+00 1.28E+00 9.15E-01 Ru-106 1.70E+00 1.62E+00 1.26E+00 8.99E-01

I-131 6.67E+02 5.04E+01 2.91E-04 3.49E-11 I-131 6.57E+02 4.96E+01 2.86E-04 3.43E-11

Cs-134 9.37E-01 9.13E-01 8.10E-01 6.92E-01 Cs-134 9.22E-01 8.99E-01 7.97E-01 6.80E-01

Cs-137 1.02E+00 1.02E+00 1.02E+00 1.02E+00 Cs-137 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Ce-141 5.03E+01 2.66E+01 1.35E+00 2.65E-02 Ce-141 4.95E+01 2.61E+01 1.33E+00 2.61E-02

Ce-144 2.57E+01 2.39E+01 1.72E+01 1.11E+01 Ce-144 2.53E+01 2.36E+01 1.69E+01 1.09E+01

Pr-143 4.03E+01 8.74E+00 6.91E-03 5.51E-07 Pr-143 3.97E+01 8.60E+00 6.80E-03 5.41E-07

Pm-147 2.81E+00 2.87E+00 2.64E+00 2.34E+00 Pm-147 2.77E+00 2.83E+00 2.60E+00 2.30E+00
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 26 of 100

Table 2-5 values: Mark 16 2

Nuclide

Intake relative to Sr-90

Nuclide

Intake relative to Cs-137

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 5.90E+01 3.92E+01 5.80E+00 4.64E-01 Sr-89 5.82E+01 3.87E+01 5.72E+00 4.58E-01

Sr-90 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Sr-90 9.87E-01 9.87E-01 9.87E-01 9.86E-01

Y-91 7.13E+01 5.01E+01 9.63E+00 1.09E+00 Y-91 7.04E+01 4.95E+01 9.51E+00 1.07E+00

Zr-95 7.77E+01 5.62E+01 1.25E+01 1.70E+00 Zr-95 7.67E+01 5.55E+01 1.23E+01 1.68E+00

Nb-95 7.18E+01 6.90E+01 2.40E+01 3.66E+00 Nb-95 7.08E+01 6.81E+01 2.37E+01 3.61E+00

Ru-103 3.91E+01 2.31E+01 1.97E+00 7.60E-02 Ru-103 3.86E+01 2.28E+01 1.94E+00 7.50E-02

Ru-106 1.77E+00 1.68E+00 1.30E+00 9.34E-01 Ru-106 1.75E+00 1.66E+00 1.29E+00 9.21E-01

I-131 1.01E+03 7.60E+01 4.39E-04 5.27E-11 I-131 9.94E+02 7.50E+01 4.34E-04 5.19E-11

Cs-134 5.65E-01 5.51E-01 4.89E-01 4.17E-01 Cs-134 5.58E-01 5.44E-01 4.82E-01 4.12E-01

Cs-137 1.01E+00 1.01E+00 1.01E+00 1.01E+00 Cs-137 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Ce-141 7.36E+01 3.89E+01 1.98E+00 3.88E-02 Ce-141 7.26E+01 3.84E+01 1.96E+00 3.83E-02

Ce-144 2.80E+01 2.61E+01 1.87E+01 1.21E+01 Ce-144 2.77E+01 2.58E+01 1.85E+01 1.19E+01

Pr-143 6.12E+01 1.33E+01 1.05E-02 8.36E-07 Pr-143 6.04E+01 1.31E+01 1.04E-02 8.24E-07

Pm-147 3.17E+00 3.29E+00 3.03E+00 2.68E+00 Pm-147 3.13E+00 3.24E+00 2.99E+00 2.64E+00

Table 2-5 values: Mark VI-B 1

Nuclide

Intake relative to Sr-90

Nuclide

Intake relative to Cs-137

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 5.36E+01 3.56E+01 5.27E+00 4.22E-01 Sr-89 5.30E+01 3.52E+01 5.20E+00 4.16E-01

Sr-90 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Sr-90 9.89E-01 9.88E-01 9.88E-01 9.87E-01

Y-91 6.53E+01 4.59E+01 8.81E+00 9.97E-01 Y-91 6.45E+01 4.53E+01 8.71E+00 9.84E-01

Zr-95 7.14E+01 5.17E+01 1.15E+01 1.56E+00 Zr-95 7.05E+01 5.11E+01 1.13E+01 1.54E+00

Nb-95 6.85E+01 6.48E+01 2.21E+01 3.37E+00 Nb-95 6.77E+01 6.41E+01 2.19E+01 3.32E+00

Ru-103 3.49E+01 2.06E+01 1.76E+00 6.79E-02 Ru-103 3.45E+01 2.04E+01 1.74E+00 6.70E-02

Ru-106 1.71E+00 1.62E+00 1.26E+00 9.01E-01 Ru-106 1.69E+00 1.60E+00 1.24E+00 8.89E-01

I-131 8.82E+02 6.66E+01 3.85E-04 4.61E-11 I-131 8.72E+02 6.58E+01 3.80E-04 4.55E-11

Cs-134 8.30E-01 8.09E-01 7.18E-01 6.13E-01 Cs-134 8.20E-01 7.99E-01 7.09E-01 6.05E-01

Cs-137 1.01E+00 1.01E+00 1.01E+00 1.01E+00 Cs-137 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Ce-141 6.55E+01 3.46E+01 1.76E+00 3.45E-02 Ce-141 6.47E+01 3.42E+01 1.74E+00 3.41E-02

Ce-144 2.73E+01 2.54E+01 1.83E+01 1.18E+01 Ce-144 2.70E+01 2.52E+01 1.81E+01 1.16E+01

Pr-143 5.36E+01 1.16E+01 9.20E-03 7.33E-07 Pr-143 5.30E+01 1.15E+01 9.09E-03 7.24E-07

Pm-147 2.88E+00 2.97E+00 2.74E+00 2.43E+00 Pm-147 2.84E+00 2.94E+00 2.71E+00 2.39E+00
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 27 of 100

Table 2-5 values: Mark VI-B 2

Nuclide

Intake relative to Sr-90

Nuclide

Intake relative to Cs-137

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 5.36E+01 3.56E+01 5.27E+00 4.22E-01 Sr-89 5.30E+01 3.52E+01 5.21E+00 4.17E-01

Sr-90 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Sr-90 9.89E-01 9.89E-01 9.89E-01 9.88E-01

Y-91 6.53E+01 4.59E+01 8.82E+00 9.98E-01 Y-91 6.46E+01 4.54E+01 8.72E+00 9.86E-01

Zr-95 7.14E+01 5.17E+01 1.15E+01 1.57E+00 Zr-95 7.06E+01 5.11E+01 1.13E+01 1.55E+00

Nb-95 6.85E+01 6.48E+01 2.21E+01 3.37E+00 Nb-95 6.78E+01 6.41E+01 2.19E+01 3.33E+00

Ru-103 3.49E+01 2.06E+01 1.75E+00 6.78E-02 Ru-103 3.45E+01 2.04E+01 1.73E+00 6.69E-02

Ru-106 1.69E+00 1.60E+00 1.24E+00 8.92E-01 Ru-106 1.67E+00 1.58E+00 1.23E+00 8.81E-01

I-131 8.83E+02 6.66E+01 3.85E-04 4.62E-11 I-131 8.74E+02 6.59E+01 3.81E-04 4.56E-11

Cs-134 6.72E-01 6.55E-01 5.81E-01 4.97E-01 Cs-134 6.65E-01 6.48E-01 5.75E-01 4.91E-01

Cs-137 1.01E+00 1.01E+00 1.01E+00 1.01E+00 Cs-137 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Ce-141 6.56E+01 3.46E+01 1.77E+00 3.46E-02 Ce-141 6.49E+01 3.43E+01 1.75E+00 3.42E-02

Ce-144 2.73E+01 2.54E+01 1.83E+01 1.18E+01 Ce-144 2.70E+01 2.52E+01 1.81E+01 1.17E+01

Pr-143 5.39E+01 1.17E+01 9.24E-03 7.37E-07 Pr-143 5.33E+01 1.16E+01 9.14E-03 7.28E-07

Pm-147 3.03E+00 3.13E+00 2.88E+00 2.55E+00 Pm-147 3.00E+00 3.10E+00 2.85E+00 2.52E+00

Table 2-6. Urine activity fractions for raw urine samples.

Nuclide

Fraction of beta activity in urine: Mk V-B Fraction of beta activity in urine: Mk 16 1 Fraction of beta activity in urine: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90 1.28E-02 2.05E-02 9.46E-02 2.12E-01 3.19E-02 4.62E-02 1.36E-01 2.10E-01 2.43E-02 3.62E-02 1.28E-01 2.24E-01

Nuclide

Fraction of gamma activity in urine: Mk V-B Fraction of gamma activity in urine: Mk 16 1 Fraction of gamma activity in urine: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Cs-137 9.02E-02 2.37E-01 6.81E-01 8.27E-01 1.87E-01 2.62E-01 3.51E-01 4.00E-01 1.77E-01 2.94E-01 4.54E-01 5.21E-01

Nuclide

Fraction of beta activity in urine: Mk VI-B 1 Fraction of beta activity in urine: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90 2.62E-02 3.87E-02 1.28E-01 2.12E-01 2.64E-02 3.90E-02 1.31E-01 2.20E-01

Nuclide

Fraction of gamma activity in urine: Mk VI-B 1 Fraction of gamma activity in urine: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Cs-137 1.72E-01 2.61E-01 3.73E-01 4.28E-01 1.82E-01 2.85E-01 4.19E-01 4.78E-01

Table 2-7. Urine activity fractions for urine samples after major chemical processing.

Nuclide

Fraction of beta activity in urine: Mk V-B Fraction of beta activity in urine: Mk 16 1 Fraction of beta activity in urine: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90 1.40E-02 2.28E-02 1.26E-01 4.18E-01 3.69E-02 5.60E-02 2.32E-01 5.10E-01 2.70E-02 4.15E-02 1.92E-01 4.83E-01

Nuclide

Fraction of beta activity in urine: Mk VI-B 1 Fraction of beta activity in urine: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90 2.96E-02 4.54E-02 2.04E-01 4.92E-01 2.96E-02 4.53E-02 2.04E-01 4.92E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 28 of 100

Table 2-8. Activity ratios for use if gross beta or gross gamma results are reported for air samples and workplace measurements.

Nuclide

Fraction of beta activity on air sample: Mk V-B Fraction of beta activity on air sample: Mk 16 1 Fraction of beta activity on air sample: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90 6.24E-04 1.46E-03 7.02E-03 1.63E-02 2.15E-03 3.86E-03 1.19E-02 2.30E-02 1.57E-03 2.97E-03 1.03E-02 2.11E-02

Nuclide

Fraction of gamma activity on air sample: Mk V-B Fraction of gamma activity on air sample: Mk 16 1 Fraction of gamma activity on air sample: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Cs-137 9.22E-04 2.37E-03 1.33E-02 7.18E-02 3.05E-03 5.91E-03 2.58E-02 1.06E-01 2.20E-03 4.43E-03 2.04E-02 9.54E-02

Nuclide

Fraction of beta activity on air sample: Mk VI-B 1 Fraction of beta activity on air sample: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90 1.73E-03 3.22E-03 1.08E-02 2.17E-02 1.73E-03 3.22E-03 1.08E-02 2.17E-02

Nuclide

Fraction of gamma activity on air sample: Mk VI-B 1 Fraction of gamma activity on air sample: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Cs-137 2.42E-03 4.82E-03 2.17E-02 9.59E-02 2.42E-03 4.82E-03 2.19E-02 9.86E-02
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 29 of 100

Table 2-9. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, minimally processed samples at 10 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 1.27E-04 Mk V-B soluble 5.64E-05 -55.67%

Urinary bladder FFTF 2 soluble 2.65E-04 Mk V-B soluble 2.58E-04 -2.71%

Brain FFTF 2 soluble 1.27E-04 Mk V-B soluble 7.29E-05 -42.79%

Breast FFTF 2 soluble 1.02E-04 Mk V-B soluble 4.01E-05 -60.81%

Gall bladder FFTF 2 soluble 1.12E-04 Mk V-B soluble 4.27E-05 -62.03%

Heart wall FFTF 2 soluble 1.18E-04 Mk V-B soluble 5.15E-05 -56.49%

Kidneys FFTF 2 soluble 1.17E-04 Mk V-B soluble 4.96E-05 -57.64%

Liver FFTF 2 soluble 8.81E-04 Mk 16 1 soluble 5.74E-04 -34.84%

Muscle FFTF 2 soluble 1.24E-04 Mk V-B soluble 6.58E-05 -46.92%

Ovaries FFTF 2 soluble 1.25E-04 Mk V-B soluble 5.40E-05 -56.64%

Pancreas FFTF 2 soluble 1.17E-04 Mk V-B soluble 4.72E-05 -59.49%

Testes FFTF 2 soluble 9.64E-05 Mk V-B soluble 3.19E-05 -66.90%

Thyroid ATR 2 soluble 1.23E-01 Mk V-B soluble 1.29E-01 5.12%

Red bone marrow FFTF 2 soluble 4.31E-04 Mk 16 1 soluble 3.32E-04 -22.97%

Bone surface FFTF 2 soluble 1.32E-03 Mk 16 1 soluble 1.10E-03 -16.54%

Stomach FFTF 2 soluble 1.29E-04 Mk V-B soluble 6.58E-05 -49.11%

Small intestine FFTF 2 soluble 1.77E-04 Mk V-B soluble 1.12E-04 -36.41%

Upper large intestine FFTF 2 soluble 3.18E-04 Mk V-B soluble 2.01E-04 -36.67%

Lower large intestine FFTF 2 insoluble 7.77E-04 Mk V-B insoluble 5.17E-04 -33.51%

Skin FFTF 2 soluble 1.02E-04 Mk V-B soluble 4.23E-05 -58.51%

Spleen FFTF 2 soluble 1.08E-04 Mk V-B soluble 4.06E-05 -62.24%

Thymus FFTF 2 soluble 1.30E-04 Mk V-B soluble 7.27E-05 -43.86%

Uterus FFTF 2 soluble 1.16E-04 Mk V-B soluble 4.83E-05 -58.21%

Extrathoracic airways FFTF 2 insoluble 1.38E-03 Mk V-B insoluble 1.18E-03 -14.80%

Lung FFTF 2 insoluble 4.88E-03 Mk 16 1 insoluble 2.50E-03 -48.71%

Colon FFTF 2 insoluble 5.02E-04 Mk V-B insoluble 3.36E-04 -33.11%

Esophagus FFTF 2 soluble 1.30E-04 Mk V-B soluble 7.27E-05 -43.86%

Gonads FFTF 2 soluble 1.25E-04 Mk V-B soluble 5.40E-05 -56.64%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 30 of 100

Table 2-10. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, minimally processed samples at 40 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 1.33E-04 Mk 16 1 soluble 5.59E-05 -58.02%

Urinary bladder FFTF 2 soluble 1.41E-04 Mk V-B soluble 6.53E-05 -53.76%

Brain FFTF 2 soluble 1.15E-04 Mk V-B soluble 4.05E-05 -64.64%

Breast FFTF 2 soluble 1.06E-04 Mk 16 1 soluble 3.30E-05 -69.01%

Gall bladder FFTF 2 soluble 1.20E-04 Mk 16 1 soluble 4.10E-05 -65.74%

Heart wall FFTF 2 soluble 1.20E-04 Mk 16 1 soluble 4.29E-05 -64.40%

Kidneys FFTF 2 soluble 1.23E-04 Mk 16 1 soluble 4.63E-05 -62.43%

Liver FFTF 2 soluble 1.04E-03 Mk 16 1 soluble 7.41E-04 -28.59%

Muscle FFTF 2 soluble 1.15E-04 Mk 16 1 soluble 3.92E-05 -65.99%

Ovaries FFTF 2 soluble 1.29E-04 Mk 16 1 soluble 5.12E-05 -60.45%

Pancreas FFTF 2 soluble 1.23E-04 Mk 16 1 soluble 4.41E-05 -64.01%

Testes FFTF 2 soluble 1.04E-04 Mk 16 1 soluble 2.89E-05 -72.29%

Thyroid ATR 2 soluble 1.49E-02 Mk V-B soluble 1.57E-02 5.19%

Red bone marrow FFTF 2 soluble 4.58E-04 Mk 16 1 soluble 3.78E-04 -17.45%

Bone surface N Rx 2 soluble 1.38E-03 Mk 16 1 soluble 1.23E-03 -11.05%

Stomach FFTF 2 soluble 1.25E-04 Mk 16 1 soluble 4.61E-05 -63.23%

Small intestine FFTF 2 soluble 1.59E-04 Mk 16 1 soluble 7.34E-05 -53.72%

Upper large intestine FFTF 2 soluble 3.25E-04 Mk 16 1 soluble 2.01E-04 -38.26%

Lower large intestine FFTF 2 insoluble 7.98E-04 Mk 16 1 insoluble 5.24E-04 -34.37%

Skin FFTF 2 soluble 1.04E-04 Mk 16 1 soluble 3.07E-05 -70.39%

Spleen FFTF 2 soluble 1.14E-04 Mk 16 1 soluble 3.74E-05 -67.25%

Thymus FFTF 2 soluble 1.16E-04 Mk 16 1 soluble 3.95E-05 -66.01%

Uterus FFTF 2 soluble 1.19E-04 Mk 16 1 soluble 4.10E-05 -65.61%

Extrathoracic airways FFTF 2 insoluble 1.04E-03 Mk V-B insoluble 7.30E-04 -30.06%

Lung FFTF 2 insoluble 5.26E-03 Mk 16 1 insoluble 2.75E-03 -47.75%

Colon FFTF 2 insoluble 5.12E-04 Mk 16 1 insoluble 3.35E-04 -34.47%

Esophagus FFTF 2 soluble 1.16E-04 Mk 16 1 soluble 3.95E-05 -66.01%

Gonads FFTF 2 soluble 1.29E-04 Mk 16 1 soluble 5.12E-05 -60.45%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 31 of 100

Table 2-11. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, minimally processed samples at 180 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 1.43E-04 Mk V-B soluble 8.12E-05 -43.01%

Urinary bladder FFTF 2 soluble 1.47E-04 Mk V-B soluble 6.45E-05 -56.23%

Brain FFTF 2 soluble 1.28E-04 Mk V-B soluble 6.04E-05 -52.97%

Breast FFTF 2 soluble 1.26E-04 Mk V-B soluble 5.53E-05 -55.96%

Gall bladder FFTF 2 soluble 1.38E-04 Mk V-B soluble 6.54E-05 -52.67%

Heart wall FFTF 2 soluble 1.37E-04 Mk V-B soluble 6.72E-05 -50.79%

Kidneys FFTF 2 soluble 1.37E-04 Mk V-B soluble 7.01E-05 -48.84%

Liver N Rx 2 soluble 1.67E-03 Mk 16 2 soluble 1.53E-03 -8.40%

Muscle FFTF 2 soluble 1.31E-04 Mk V-B soluble 6.07E-05 -53.59%

Ovaries FFTF 2 soluble 1.40E-04 Mk V-B soluble 7.57E-05 -45.90%

Pancreas FFTF 2 soluble 1.38E-04 Mk V-B soluble 6.79E-05 -50.95%

Testes FFTF 2 soluble 1.26E-04 Mk V-B soluble 4.98E-05 -60.56%

Thyroid FFTF 2 soluble 1.30E-04 Mk V-B soluble 5.90E-05 -54.76%

Red bone marrow N Rx 2 soluble 6.32E-04 Mk 16 2 soluble 5.93E-04 -6.19%

Bone surface TRIGA 2 soluble 1.81E-03 Mk V-B soluble 1.69E-03 -6.93%

Stomach FFTF 2 soluble 1.42E-04 Mk V-B soluble 7.10E-05 -50.16%

Small intestine FFTF 2 soluble 1.67E-04 Mk V-B soluble 1.05E-04 -37.41%

Upper large intestine FFTF 2 soluble 3.31E-04 Mk V-B soluble 2.81E-04 -14.93%

Lower large intestine FFTF 2 insoluble 7.93E-04 Mk V-B insoluble 7.26E-04 -8.34%

Skin FFTF 2 soluble 1.23E-04 Mk V-B soluble 5.17E-05 -58.06%

Spleen FFTF 2 soluble 1.33E-04 Mk V-B soluble 6.01E-05 -54.68%

Thymus FFTF 2 soluble 1.32E-04 Mk V-B soluble 6.14E-05 -53.43%

Uterus FFTF 2 soluble 1.35E-04 Mk V-B soluble 6.34E-05 -53.20%

Extrathoracic airways TRIGA 2 insoluble 1.01E-03 Mk V-B insoluble 9.78E-04 -3.66%

Lung FFTF 2 insoluble 5.74E-03 Mk V-B insoluble 4.44E-03 -22.72%

Colon FFTF 2 insoluble 5.08E-04 Mk V-B insoluble 4.63E-04 -8.78%

Esophagus FFTF 2 soluble 1.32E-04 Mk V-B soluble 6.14E-05 -53.43%

Gonads FFTF 2 soluble 1.40E-04 Mk V-B soluble 7.57E-05 -45.90%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 32 of 100

Table 2-12. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, minimally processed samples at 1 year decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 1.20E-04 Mk V-B soluble 7.74E-05 -35.35%

Urinary bladder FFTF 2 soluble 1.29E-04 Mk V-B soluble 7.35E-05 -42.86%

Brain FFTF 2 soluble 1.10E-04 Mk V-B soluble 6.62E-05 -40.10%

Breast FFTF 2 soluble 1.09E-04 Mk V-B soluble 6.48E-05 -40.62%

Gall bladder FFTF 2 soluble 1.20E-04 Mk V-B soluble 7.37E-05 -38.54%

Heart wall FFTF 2 soluble 1.17E-04 Mk V-B soluble 7.23E-05 -38.41%

Kidneys FFTF 2 soluble 1.17E-04 Mk V-B soluble 7.24E-05 -38.06%

Liver TRIGA 2 soluble 2.01E-03 Mk V-B soluble 1.97E-03 -1.83%

Muscle FFTF 2 soluble 1.13E-04 Mk V-B soluble 6.76E-05 -40.13%

Ovaries FFTF 2 soluble 1.18E-04 Mk V-B soluble 7.40E-05 -37.31%

Pancreas FFTF 2 soluble 1.19E-04 Mk V-B soluble 7.30E-05 -38.79%

Testes FFTF 2 soluble 1.11E-04 Mk V-B soluble 6.34E-05 -43.10%

Thyroid FFTF 2 soluble 1.13E-04 Mk V-B soluble 6.68E-05 -40.92%

Red bone marrow TRIGA 2 soluble 7.50E-04 Mk V-B soluble 7.17E-04 -4.45%

Bone surface TRIGA 2 soluble 1.81E-03 Mk V-B soluble 1.73E-03 -4.69%

Stomach FFTF 2 soluble 1.23E-04 Mk V-B soluble 7.99E-05 -34.90%

Small intestine FFTF 2 soluble 1.40E-04 Mk V-B soluble 1.07E-04 -23.45%

Upper large intestine N Rx 1 soluble 2.82E-04 Mk V-B soluble 2.91E-04 2.96%

Lower large intestine N Rx 1 insoluble 7.32E-04 Mk V-B insoluble 7.54E-04 2.98%

Skin FFTF 2 soluble 1.08E-04 Mk V-B soluble 6.27E-05 -41.79%

Spleen FFTF 2 soluble 1.15E-04 Mk V-B soluble 6.84E-05 -40.58%

Thymus FFTF 2 soluble 1.14E-04 Mk V-B soluble 6.86E-05 -39.86%

Uterus FFTF 2 soluble 1.17E-04 Mk V-B soluble 6.98E-05 -40.38%

Extrathoracic airways TRIGA 2 insoluble 8.95E-04 Mk V-B insoluble 8.97E-04 0.31%

Lung N Rx 1 insoluble 5.03E-03 Mk V-B insoluble 5.28E-03 4.87%

Colon N Rx 1 insoluble 4.66E-04 Mk V-B insoluble 4.79E-04 2.80%

Esophagus FFTF 2 soluble 1.14E-04 Mk V-B soluble 6.86E-05 -39.86%

Gonads FFTF 2 soluble 1.18E-04 Mk V-B soluble 7.40E-05 -37.31%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 33 of 100

Table 2-13. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, significantly processed samples at 10 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 2.83E-04 Mk 16 1 soluble 6.27E-05 -77.80%

Urinary bladder FFTF 1 soluble 5.17E-04 Mk V-B soluble 2.81E-04 -45.60%

Brain FFTF 1 soluble 2.75E-04 Mk V-B soluble 7.96E-05 -71.01%

Breast FFTF 1 soluble 2.31E-04 Mk V-B soluble 4.38E-05 -81.04%

Gall bladder FFTF 1 soluble 2.58E-04 Mk V-B soluble 4.67E-05 -81.94%

Heart wall FFTF 1 soluble 2.66E-04 Mk V-B soluble 5.63E-05 -78.84%

Kidneys FFTF 1 soluble 2.63E-04 Mk V-B soluble 5.42E-05 -79.41%

Liver FFTF 1 soluble 1.95E-03 Mk 16 1 soluble 6.64E-04 -65.98%

Muscle FFTF 1 soluble 2.71E-04 Mk V-B soluble 7.19E-05 -73.50%

Ovaries FFTF 1 soluble 2.77E-04 Mk V-B soluble 5.90E-05 -78.70%

Pancreas FFTF 1 soluble 2.65E-04 Mk V-B soluble 5.16E-05 -80.51%

Testes FFTF 1 soluble 2.24E-04 Mk V-B soluble 3.48E-05 -84.43%

Thyroid FFTF 2 soluble 1.66E-01 Mk V-B soluble 1.41E-01 -14.96%

Red bone marrow FFTF 1 soluble 9.26E-04 Mk 16 1 soluble 3.84E-04 -58.54%

Bone surface FFTF 1 soluble 2.64E-03 Mk 16 1 soluble 1.27E-03 -51.90%

Stomach FFTF 1 soluble 2.85E-04 Mk V-B soluble 7.18E-05 -74.83%

Small intestine FFTF 1 soluble 3.74E-04 Mk V-B soluble 1.23E-04 -67.23%

Upper large intestine FFTF 1 soluble 6.69E-04 Mk 16 1 soluble 2.27E-04 -66.10%

Lower large intestine FFTF 1 insoluble 1.61E-03 Mk 16 1 Insoluble 5.88E-04 -63.44%

Skin FFTF 1 soluble 2.29E-04 Mk V-B soluble 4.62E-05 -79.82%

Spleen FFTF 1 soluble 2.46E-04 Mk V-B soluble 4.44E-05 -81.95%

Thymus FFTF 1 soluble 2.82E-04 Mk V-B soluble 7.94E-05 -71.82%

Uterus FFTF 1 soluble 2.61E-04 Mk V-B soluble 5.27E-05 -79.83%

Extrathoracic airways FFTF 1 insoluble 2.64E-03 Mk V-B insoluble 1.28E-03 -51.31%

Lung FFTF 1 insoluble 1.03E-02 Mk 16 1 insoluble 2.89E-03 -71.96%

Colon FFTF 1 insoluble 1.04E-03 Mk 16 1 insoluble 3.79E-04 -63.68%

Esophagus FFTF 1 soluble 2.82E-04 Mk V-B soluble 7.94E-05 -71.82%

Gonads FFTF 1 soluble 2.77E-04 Mk V-B soluble 5.90E-05 -78.70%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 34 of 100

Table 2-14. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, significantly processed samples at 40 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 3.48E-04 Mk 16 1 soluble 6.78E-05 -80.50%

Urinary bladder FFTF 1 soluble 3.67E-04 Mk V-B soluble 7.26E-05 -80.19%

Brain FFTF 1 soluble 3.01E-04 Mk 16 1 soluble 4.84E-05 -83.90%

Breast FFTF 1 soluble 2.83E-04 Mk 16 1 soluble 4.00E-05 -85.89%

Gall bladder FFTF 1 soluble 3.23E-04 Mk 16 1 soluble 4.97E-05 -84.61%

Heart wall FFTF 1 soluble 3.21E-04 Mk 16 1 soluble 5.20E-05 -83.80%

Kidneys FFTF 1 soluble 3.25E-04 Mk 16 1 soluble 5.61E-05 -82.76%

Liver FFTF 1 soluble 2.61E-03 Mk 16 1 soluble 8.99E-04 -65.54%

Muscle FFTF 1 soluble 3.05E-04 Mk 16 1 soluble 4.75E-05 -84.43%

Ovaries FFTF 1 soluble 3.39E-04 Mk 16 1 soluble 6.21E-05 -81.68%

Pancreas FFTF 1 soluble 3.27E-04 Mk 16 1 soluble 5.34E-05 -83.68%

Testes FFTF 1 soluble 2.83E-04 Mk 16 1 soluble 3.50E-05 -87.63%

Thyroid FFTF 2 soluble 1.94E-02 Mk V-B soluble 1.74E-02 -10.19%

Red bone marrow FFTF 1 soluble 1.15E-03 Mk 16 1 soluble 4.58E-04 -60.08%

Bone surface FFTF 1 soluble 3.17E-03 Mk 16 1 soluble 1.49E-03 -53.09%

Stomach FFTF 1 soluble 3.32E-04 Mk 16 1 soluble 5.59E-05 -83.16%

Small intestine FFTF 1 soluble 4.07E-04 Mk 16 1 soluble 8.90E-05 -78.14%

Upper large intestine FFTF 1 soluble 8.00E-04 Mk 16 1 soluble 2.44E-04 -69.56%

Lower large intestine FFTF 1 insoluble 1.92E-03 Mk 16 1 insoluble 6.35E-04 -66.94%

Skin FFTF 1 soluble 2.76E-04 Mk 16 1 soluble 3.73E-05 -86.52%

Spleen FFTF 1 soluble 3.06E-04 Mk 16 1 soluble 4.53E-05 -85.21%

Thymus FFTF 1 soluble 3.09E-04 Mk 16 1 soluble 4.79E-05 -84.49%

Uterus FFTF 1 soluble 3.19E-04 Mk 16 1 soluble 4.97E-05 -84.43%

Extrathoracic airways FFTF 1 insoluble 2.40E-03 Mk 16 1 insoluble 8.81E-04 -63.32%

Lung FFTF 1 insoluble 1.28E-02 Mk 16 1 insoluble 3.33E-03 -74.05%

Colon FFTF 1 insoluble 1.24E-03 Mk 16 1 insoluble 4.07E-04 -67.19%

Esophagus FFTF 1 soluble 3.09E-04 Mk 16 1 soluble 4.79E-05 -84.49%

Gonads FFTF 1 soluble 3.39E-04 Mk 16 1 soluble 6.21E-05 -81.68%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 35 of 100

Table 2-15. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis, significantly processed samples at 180 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 6.02E-04 Mk 16 1 soluble 1.12E-04 -81.34%

Urinary bladder FFTF 2 soluble 6.23E-04 Mk 16 1 soluble 9.26E-05 -85.14%

Brain FFTF 2 soluble 5.43E-04 Mk 16 1 soluble 8.51E-05 -84.32%

Breast FFTF 2 soluble 5.31E-04 Mk 16 1 soluble 7.96E-05 -85.00%

Gall bladder FFTF 2 soluble 5.84E-04 Mk 16 1 soluble 9.65E-05 -83.46%

Heart wall FFTF 2 soluble 5.77E-04 Mk 16 1 soluble 9.71E-05 -83.17%

Kidneys FFTF 2 soluble 5.79E-04 Mk 16 1 soluble 9.90E-05 -82.89%

Liver FFTF 2 soluble 5.35E-03 Mk 16 1 soluble 2.54E-03 -52.61%

Muscle FFTF 2 soluble 5.52E-04 Mk 16 1 soluble 8.70E-05 -84.25%

Ovaries FFTF 2 soluble 5.91E-04 Mk 16 1 soluble 1.05E-04 -82.16%

Pancreas FFTF 2 soluble 5.85E-04 Mk 16 1 soluble 9.85E-05 -83.17%

Testes FFTF 2 soluble 5.34E-04 Mk 16 1 soluble 7.51E-05 -85.93%

Thyroid FFTF 2 soluble 5.51E-04 Mk 16 1 soluble 8.54E-05 -84.49%

Red bone marrow FFTF 2 soluble 2.00E-03 Mk 16 1 soluble 9.73E-04 -51.43%

Bone surface FFTF 2 soluble 4.79E-03 Mk 16 1 soluble 2.56E-03 -46.58%

Stomach FFTF 2 soluble 6.02E-04 Mk 16 1 soluble 1.04E-04 -82.68%

Small intestine FFTF 2 soluble 7.06E-04 Mk 16 1 soluble 1.51E-04 -78.59%

Upper large intestine FFTF 2 soluble 1.40E-03 Mk 16 1 soluble 4.17E-04 -70.18%

Lower large intestine FFTF 2 insoluble 3.35E-03 Mk 16 1 insoluble 1.07E-03 -67.90%

Skin FFTF 2 soluble 5.21E-04 Mk 16 1 soluble 7.45E-05 -85.70%

Spleen FFTF 2 soluble 5.60E-04 Mk 16 1 soluble 8.79E-05 -84.30%

Thymus FFTF 2 soluble 5.57E-04 Mk 16 1 soluble 8.90E-05 -84.02%

Uterus FFTF 2 soluble 5.72E-04 Mk 16 1 soluble 9.25E-05 -83.84%

Extrathoracic airways FFTF 2 insoluble 3.62E-03 Mk 16 1 insoluble 1.39E-03 -61.56%

Lung FFTF 2 insoluble 2.42E-02 Mk 16 1 insoluble 6.83E-03 -71.85%

Colon FFTF 2 insoluble 2.15E-03 Mk 16 1 insoluble 6.87E-04 -67.97%

Esophagus FFTF 2 soluble 5.57E-04 Mk 16 1 soluble 8.90E-05 -84.02%

Gonads FFTF 2 soluble 5.91E-04 Mk 16 1 soluble 1.05E-04 -82.16%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 36 of 100

Table 2-16. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta urinalysis significantly processed samples at 1 year decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 7.22E-04 Mk V-B soluble 1.52E-04 -78.89%

Urinary bladder FFTF 2 soluble 7.76E-04 Mk V-B soluble 1.45E-04 -81.35%

Brain FFTF 2 soluble 6.67E-04 Mk V-B soluble 1.30E-04 -80.44%

Breast FFTF 2 soluble 6.58E-04 Mk V-B soluble 1.28E-04 -80.61%

Gall bladder FFTF 2 soluble 7.24E-04 Mk V-B soluble 1.45E-04 -79.93%

Heart wall FFTF 2 soluble 7.08E-04 Mk V-B soluble 1.42E-04 -79.89%

Kidneys FFTF 2 soluble 7.05E-04 Mk V-B soluble 1.43E-04 -79.78%

Liver FFTF 2 soluble 6.23E-03 Mk V-B soluble 3.88E-03 -37.71%

Muscle FFTF 2 soluble 6.81E-04 Mk V-B soluble 1.33E-04 -80.45%

Ovaries FFTF 2 soluble 7.12E-04 Mk V-B soluble 1.46E-04 -79.53%

Pancreas FFTF 2 soluble 7.20E-04 Mk V-B soluble 1.44E-04 -80.02%

Testes FFTF 2 soluble 6.72E-04 Mk V-B soluble 1.25E-04 -81.42%

Thyroid FFTF 2 soluble 6.83E-04 Mk V-B soluble 1.32E-04 -80.71%

Red bone marrow FFTF 2 soluble 2.42E-03 Mk V-B soluble 1.41E-03 -41.72%

Bone surface FFTF 2 soluble 5.32E-03 Mk V-B soluble 3.40E-03 -35.95%

Stomach FFTF 2 soluble 7.41E-04 Mk V-B soluble 1.57E-04 -78.74%

Small intestine FFTF 2 soluble 8.45E-04 Mk V-B soluble 2.11E-04 -75.01%

Upper large intestine FFTF 2 soluble 1.61E-03 Mk V-B soluble 5.73E-04 -64.49%

Lower large intestine FFTF 2 insoluble 3.81E-03 Mk V-B insoluble 1.49E-03 -61.05%

Skin FFTF 2 soluble 6.50E-04 Mk V-B soluble 1.23E-04 -80.99%

Spleen FFTF 2 soluble 6.94E-04 Mk V-B soluble 1.35E-04 -80.60%

Thymus FFTF 2 soluble 6.88E-04 Mk V-B soluble 1.35E-04 -80.36%

Uterus FFTF 2 soluble 7.07E-04 Mk V-B soluble 1.38E-04 -80.54%

Extrathoracic airways FFTF 2 insoluble 3.82E-03 Mk V-B insoluble 1.77E-03 -53.77%

Lung FFTF 2 insoluble 2.82E-02 Mk V-B insoluble 1.04E-02 -63.11%

Colon FFTF 2 insoluble 2.45E-03 Mk V-B insoluble 9.43E-04 -61.53%

Esophagus FFTF 2 soluble 6.88E-04 Mk V-B soluble 1.35E-04 -80.36%

Gonads FFTF 2 soluble 7.12E-04 Mk V-B soluble 1.46E-04 -79.53%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 37 of 100

Table 2-17. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma urinalysis, minimally processed samples at 10 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals TRIGA 2 soluble 2.97E-04 Mk V-B soluble 2.59E-04 -12.81%

Urinary bladder ATR 2 soluble 9.68E-04 Mk V-B soluble 1.05E-03 8.76%

Brain TRIGA 2 soluble 2.97E-04 Mk V-B soluble 2.98E-04 0.34%

Breast TRIGA 2 soluble 1.84E-04 Mk V-B soluble 1.64E-04 -10.99%

Gall bladder TRIGA 2 soluble 2.11E-04 Mk 16 2 soluble 1.78E-04 -15.68%

Heart wall TRIGA 2 soluble 2.42E-04 Mk V-B soluble 2.11E-04 -12.89%

Kidneys TRIGA 2 soluble 2.50E-04 Mk 16 2 soluble 2.07E-04 -16.95%

Liver N Rx 2 soluble 2.73E-03 Mk 16 2 soluble 2.31E-03 -15.18%

Muscle TRIGA 2 soluble 2.73E-04 Mk V-B soluble 2.69E-04 -1.45%

Ovaries TRIGA 2 soluble 2.75E-04 Mk 16 2 soluble 2.29E-04 -16.85%

Pancreas TRIGA 2 soluble 2.34E-04 Mk 16 2 soluble 1.96E-04 -16.39%

Testes FFTF 2 soluble 1.61E-04 Mk V-B soluble 1.30E-04 -18.89%

Thyroid ATR 2 soluble 4.91E-01 Mk V-B soluble 5.28E-01 7.64%

Red bone marrow TRIGA 2 soluble 1.71E-03 Mk 16 2 soluble 1.46E-03 -14.35%

Bone surface TRIGA 2 soluble 6.03E-03 Mk 16 2 soluble 4.99E-03 -17.19%

Stomach TRIGA 2 soluble 2.90E-04 Mk V-B soluble 2.69E-04 -7.21%

Small intestine TRIGA 2 soluble 4.95E-04 Mk V-B soluble 4.59E-04 -7.20%

Upper large intestine TRIGA 2 soluble 1.09E-03 Mk 16 2 soluble 9.02E-04 -16.91%

Lower large intestine TRIGA 2 insoluble 2.82E-03 Mk 16 2 insoluble 2.34E-03 -16.85%

Skin N Rx 1 soluble 1.85E-04 Mk V-B soluble 1.73E-04 -6.60%

Spleen TRIGA 2 soluble 1.97E-04 Mk V-B soluble 1.66E-04 -15.52%

Thymus TRIGA 2 soluble 2.91E-04 Mk V-B soluble 2.97E-04 2.05%

Uterus TRIGA 2 soluble 2.28E-04 Mk V-B soluble 1.97E-04 -13.37%

Extrathoracic airways TRIGA 2 insoluble 5.18E-03 Mk V-B insoluble 4.81E-03 -7.26%

Lung TRIGA 2 insoluble 1.31E-02 Mk 16 2 insoluble 1.11E-02 -14.78%

Colon TRIGA 2 insoluble 1.82E-03 Mk 16 2 insoluble 1.51E-03 -16.94%

Esophagus TRIGA 2 soluble 2.91E-04 Mk V-B soluble 2.97E-04 2.05%

Gonads TRIGA 2 soluble 2.75E-04 Mk 16 2 soluble 2.29E-04 -16.85%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 38 of 100

Table 2-18. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma urinalysis, minimally processed samples at 40 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals TRIGA 2 Soluble 4.24E-04 Mk V-B Soluble 3.98E-04 -6.04%

Urinary bladder TRIGA 2 Soluble 3.97E-04 Mk V-B Soluble 4.36E-04 10.06%

Brain TRIGA 2 Soluble 2.98E-04 Mk V-B Soluble 2.71E-04 -9.07%

Breast TRIGA 2 Soluble 2.34E-04 Mk V-B Soluble 2.03E-04 -12.90%

Gall bladder TRIGA 2 Soluble 2.91E-04 Mk V-B Soluble 2.50E-04 -14.31%

Heart wall TRIGA 2 Soluble 3.10E-04 Mk V-B Soluble 2.65E-04 -14.57%

Kidneys TRIGA 2 Soluble 3.42E-04 Mk V-B Soluble 2.92E-04 -14.58%

Liver TRIGA 2 Soluble 4.59E-03 Mk 16 2 Soluble 3.38E-03 -26.46%

Muscle TRIGA 2 Soluble 2.87E-04 Mk V-B Soluble 2.58E-04 -10.02%

Ovaries TRIGA 2 Soluble 3.82E-04 Mk V-B Soluble 3.24E-04 -15.23%

Pancreas TRIGA 2 Soluble 3.20E-04 Mk V-B Soluble 2.74E-04 -14.43%

Testes TRIGA 2 Soluble 1.96E-04 Mk V-B Soluble 1.76E-04 -9.94%

Thyroid ATR 2 Soluble 9.19E-02 Mk V-B Soluble 1.05E-01 13.98%

Red bone marrow TRIGA 2 Soluble 2.73E-03 Mk V-B Soluble 2.06E-03 -24.49%

Bone surface TRIGA 2 Soluble 9.62E-03 Mk V-B Soluble 7.38E-03 -23.27%

Stomach TRIGA 2 Soluble 3.35E-04 Mk V-B Soluble 2.95E-04 -11.83%

Small intestine TRIGA 2 Soluble 5.55E-04 Mk V-B Soluble 4.84E-04 -12.94%

Upper large intestine TRIGA 2 Soluble 1.53E-03 Mk V-B Soluble 1.27E-03 -16.90%

Lower large intestine TRIGA 2 Insoluble 4.01E-03 Mk V-B Insoluble 3.35E-03 -16.58%

Skin TRIGA 2 Soluble 2.18E-04 Mk V-B Soluble 1.95E-04 -10.25%

Spleen TRIGA 2 Soluble 2.65E-04 Mk V-B Soluble 2.30E-04 -13.32%

Thymus TRIGA 2 Soluble 2.87E-04 Mk V-B Soluble 2.59E-04 -9.71%

Uterus TRIGA 2 Soluble 2.95E-04 Mk V-B Soluble 2.58E-04 -12.52%

Extrathoracic airways TRIGA 2 Insoluble 5.75E-03 Mk V-B Insoluble 4.88E-03 -15.16%

Lung TRIGA 2 Insoluble 1.99E-02 Mk V-B Insoluble 1.61E-02 -18.78%

Colon TRIGA 2 Insoluble 2.57E-03 Mk V-B Insoluble 2.14E-03 -16.54%

Esophagus TRIGA 2 Soluble 2.87E-04 Mk V-B Soluble 2.59E-04 -9.71%

Gonads TRIGA 2 Soluble 3.82E-04 Mk V-B Soluble 3.24E-04 -15.23%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 39 of 100

Table 2-19. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma urinalysis, minimally processed samples at 180 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals TRIGA 2 soluble 3.01E-04 Mk V-B soluble 3.81E-04 26.92%

Urinary bladder N Rx 1 soluble 2.33E-04 Mk V-B soluble 2.69E-04 15.60%

Brain N Rx 1 soluble 2.17E-04 Mk V-B soluble 2.52E-04 15.87%

Breast N Rx 1 soluble 2.02E-04 Mk V-B soluble 2.31E-04 14.27%

Gall bladder TRIGA 2 soluble 2.40E-04 Mk V-B soluble 2.73E-04 13.86%

Heart wall TRIGA 2 soluble 2.48E-04 Mk V-B soluble 2.80E-04 13.23%

Kidneys TRIGA 2 soluble 2.55E-04 Mk V-B soluble 2.92E-04 14.53%

Liver TRIGA 2 soluble 6.41E-03 Mk V-B soluble 5.79E-03 -9.54%

Muscle N Rx 1 soluble 2.19E-04 Mk V-B soluble 2.53E-04 15.38%

Ovaries TRIGA 2 soluble 2.76E-04 Mk V-B soluble 3.16E-04 14.48%

Pancreas TRIGA 2 soluble 2.48E-04 Mk V-B soluble 2.83E-04 14.34%

Testes N Rx 1 soluble 1.84E-04 Mk V-B soluble 2.08E-04 12.86%

Thyroid N Rx 1 soluble 2.13E-04 Mk V-B soluble 2.46E-04 15.43%

Red bone marrow TRIGA 2 soluble 2.54E-03 Mk V-B soluble 2.38E-03 -6.33%

Bone surface TRIGA 2 soluble 7.32E-03 Mk V-B soluble 7.03E-03 -3.91%

Stomach TRIGA 2 soluble 2.63E-04 Mk V-B soluble 2.96E-04 12.54%

Small intestine TRIGA 2 soluble 4.02E-04 Mk V-B soluble 4.36E-04 8.58%

Upper large intestine TRIGA 2 soluble 1.15E-03 Mk V-B soluble 1.17E-03 1.92%

Lower large intestine TRIGA 2 insoluble 2.99E-03 Mk V-B insoluble 3.03E-03 1.17%

Skin N Rx 1 soluble 1.90E-04 Mk V-B soluble 2.16E-04 13.81%

Spleen N Rx 1 soluble 2.18E-04 Mk V-B soluble 2.50E-04 14.90%

Thymus TRIGA 2 soluble 2.23E-04 Mk V-B soluble 2.56E-04 14.80%

Uterus N Rx 1 soluble 2.29E-04 Mk V-B soluble 2.64E-04 15.65%

Extrathoracic airways TRIGA 2 insoluble 4.10E-03 Mk V-B insoluble 4.08E-03 -0.53%

Lung TRIGA 2 insoluble 1.83E-02 Mk V-B insoluble 1.85E-02 0.86%

Colon TRIGA 2 insoluble 1.91E-03 Mk V-B insoluble 1.93E-03 1.15%

Esophagus TRIGA 2 soluble 2.23E-04 Mk V-B soluble 2.56E-04 14.80%

Gonads TRIGA 2 soluble 2.76E-04 Mk V-B soluble 3.16E-04 14.48%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 40 of 100

Table 2-20. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma urinalysis, minimally processed samples at 1 year decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals N Rx 1 soluble 1.53E-04 Mk V-B soluble 1.97E-04 28.91%

Urinary bladder FFTF 2 soluble 1.51E-04 Mk V-B soluble 1.66E-04 9.86%

Brain N Rx 1 soluble 1.31E-04 Mk V-B soluble 1.49E-04 13.88%

Breast N Rx 1 soluble 1.29E-04 Mk V-B soluble 1.46E-04 13.44%

Gall bladder N Rx 1 soluble 1.47E-04 Mk V-B soluble 1.66E-04 12.83%

Heart wall N Rx 1 soluble 1.44E-04 Mk V-B soluble 1.63E-04 13.62%

Kidneys N Rx 1 soluble 1.43E-04 Mk V-B soluble 1.63E-04 13.97%

Liver TRIGA 2 soluble 4.71E-03 Mk V-B soluble 4.45E-03 -5.50%

Muscle N Rx 1 soluble 1.34E-04 Mk V-B soluble 1.53E-04 13.61%

Ovaries N Rx 1 soluble 1.46E-04 Mk V-B soluble 1.67E-04 14.53%

Pancreas N Rx 1 soluble 1.45E-04 Mk V-B soluble 1.65E-04 13.47%

Testes FFTF 2 soluble 1.31E-04 Mk V-B soluble 1.43E-04 9.39%

Thyroid N Rx 1 soluble 1.33E-04 Mk V-B soluble 1.51E-04 13.40%

Red bone marrow TRIGA 2 soluble 1.76E-03 Mk V-B soluble 1.62E-03 -8.02%

Bone surface TRIGA 2 soluble 4.25E-03 Mk V-B soluble 3.90E-03 -8.26%

Stomach N Rx 1 soluble 1.61E-04 Mk V-B soluble 1.80E-04 12.20%

Small intestine N Rx 1 soluble 2.16E-04 Mk V-B soluble 2.42E-04 11.76%

Upper large intestine TRIGA 2 soluble 6.43E-04 Mk V-B soluble 6.56E-04 2.05%

Lower large intestine TRIGA 2 insoluble 1.69E-03 Mk V-B insoluble 1.70E-03 0.98%

Skin FFTF 2 soluble 1.26E-04 Mk V-B soluble 1.41E-04 11.93%

Spleen N Rx 1 soluble 1.36E-04 Mk V-B soluble 1.54E-04 13.35%

Thymus N Rx 1 soluble 1.36E-04 Mk V-B soluble 1.55E-04 13.54%

Uterus N Rx 1 soluble 1.39E-04 Mk V-B soluble 1.58E-04 13.51%

Extrathoracic airways TRIGA 2 insoluble 2.10E-03 Mk V-B insoluble 2.03E-03 -3.44%

Lung TRIGA 2 insoluble 1.15E-02 Mk V-B insoluble 1.19E-02 3.64%

Colon TRIGA 2 insoluble 1.07E-03 Mk V-B insoluble 1.08E-03 0.77%

Esophagus N Rx 1 soluble 1.36E-04 Mk V-B soluble 1.55E-04 13.54%

Gonads N Rx 1 soluble 1.46E-04 Mk V-B soluble 1.67E-04 14.53%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 41 of 100

Table 2-21. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta air samples at 10 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 1.08E-03 Mk 16 1 soluble 5.45E-04 -49.31%

Urinary bladder FFTF 1 soluble 1.97E-03 Mk V-B soluble 1.87E-03 -4.91%

Brain FFTF 1 soluble 1.04E-03 Mk V-B soluble 5.29E-04 -49.33%

Breast FFTF 1 soluble 8.79E-04 Mk 16 1 soluble 3.42E-04 -61.06%

Gall bladder FFTF 1 soluble 9.84E-04 Mk 16 1 soluble 4.01E-04 -59.21%

Heart wall FFTF 1 soluble 1.01E-03 Mk 16 1 soluble 4.45E-04 -56.02%

Kidneys FFTF 1 soluble 1.00E-03 Mk 16 1 soluble 4.60E-04 -54.08%

Liver TRIGA 1 soluble 9.29E-03 Mk 16 1 soluble 5.77E-03 -37.86%

Muscle FFTF 1 soluble 1.03E-03 Mk V-B soluble 4.78E-04 -53.67%

Ovaries FFTF 1 soluble 1.05E-03 Mk 16 1 soluble 5.06E-04 -51.99%

Pancreas FFTF 1 soluble 1.01E-03 Mk 16 1 soluble 4.37E-04 -56.60%

Testes FFTF 1 soluble 8.52E-04 Mk 16 1 soluble 2.87E-04 -66.33%

Thyroid ATR 2 soluble 9.29E-01 Mk V-B soluble 9.39E-01 1.07%

Red bone marrow TRIGA 1 soluble 5.85E-03 Mk 16 1 soluble 3.34E-03 -42.92%

Bone surface TRIGA 1 soluble 1.67E-02 Mk 16 1 soluble 1.10E-02 -33.80%

Stomach FFTF 1 soluble 1.09E-03 Mk 16 1 soluble 5.16E-04 -52.46%

Small intestine FFTF 1 soluble 1.42E-03 Mk 16 1 soluble 8.55E-04 -40.00%

Upper large intestine FFTF 1 soluble 2.55E-03 Mk 16 1 soluble 1.97E-03 -22.59%

Lower large intestine FFTF 1 insoluble 6.12E-03 Mk 16 1 insoluble 5.11E-03 -16.53%

Skin FFTF 1 soluble 8.71E-04 Mk 16 1 soluble 3.36E-04 -61.41%

Spleen FFTF 1 soluble 9.35E-04 Mk 16 1 soluble 3.71E-04 -60.30%

Thymus FFTF 1 soluble 1.07E-03 Mk V-B soluble 5.28E-04 -50.74%

Uterus FFTF 1 soluble 9.95E-04 Mk 16 1 soluble 4.21E-04 -57.65%

Extrathoracic airways FFTF 2 insoluble 1.01E-02 Mk 16 1 insoluble 8.71E-03 -13.70%

Lung FFTF 1 insoluble 3.93E-02 Mk 16 1 insoluble 2.51E-02 -35.97%

Colon FFTF 1 insoluble 3.97E-03 Mk 16 1 insoluble 3.29E-03 -17.07%

Esophagus FFTF 1 soluble 1.07E-03 Mk V-B soluble 5.28E-04 -50.74%

Gonads FFTF 1 soluble 1.05E-03 Mk 16 1 soluble 5.06E-04 -51.99%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 42 of 100

Table 2-22. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta air samples at 40 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 1.42E-03 Mk 16 1 soluble 6.97E-04 -50.90%

Urinary bladder FFTF 1 soluble 1.50E-03 Mk V-B soluble 6.93E-04 -53.68%

Brain FFTF 1 soluble 1.23E-03 Mk 16 1 soluble 4.98E-04 -59.45%

Breast FFTF 1 soluble 1.16E-03 Mk 16 1 soluble 4.11E-04 -64.47%

Gall bladder FFTF 1 soluble 1.32E-03 Mk 16 1 soluble 5.11E-04 -61.25%

Heart wall FFTF 1 soluble 1.31E-03 Mk 16 1 soluble 5.34E-04 -59.21%

Kidneys FFTF 1 soluble 1.33E-03 Mk 16 1 soluble 5.76E-04 -56.57%

Liver TRIGA 1 soluble 1.31E-02 Mk 16 1 soluble 9.24E-03 -29.50%

Muscle FFTF 1 soluble 1.25E-03 Mk 16 1 soluble 4.88E-04 -60.79%

Ovaries FFTF 1 soluble 1.38E-03 Mk 16 1 soluble 6.38E-04 -53.87%

Pancreas FFTF 1 soluble 1.34E-03 Mk 16 1 soluble 5.49E-04 -58.90%

Testes FFTF 1 soluble 1.16E-03 Mk 16 1 soluble 3.60E-04 -68.85%

Thyroid ATR 2 soluble 1.68E-01 Mk V-B soluble 1.66E-01 -1.10%

Red bone marrow TRIGA 1 soluble 8.04E-03 Mk 16 1 soluble 4.71E-03 -41.42%

Bone surface TRIGA 1 soluble 2.23E-02 Mk 16 1 soluble 1.53E-02 -31.50%

Stomach FFTF 1 soluble 1.35E-03 Mk 16 1 soluble 5.74E-04 -57.59%

Small intestine FFTF 1 soluble 1.66E-03 Mk 16 1 soluble 9.14E-04 -44.96%

Upper large intestine FFTF 1 soluble 3.27E-03 Mk 16 1 soluble 2.50E-03 -23.34%

Lower large intestine FFTF 1 insoluble 7.83E-03 Mk 16 1 insoluble 6.52E-03 -16.75%

Skin FFTF 1 soluble 1.13E-03 Mk 16 1 soluble 3.83E-04 -66.04%

Spleen FFTF 1 soluble 1.25E-03 Mk 16 1 soluble 4.65E-04 -62.75%

Thymus FFTF 1 soluble 1.26E-03 Mk 16 1 soluble 4.92E-04 -60.95%

Uterus FFTF 1 soluble 1.30E-03 Mk 16 1 soluble 5.10E-04 -60.78%

Extrathoracic airways FFTF 1 insoluble 9.81E-03 Mk 16 1 insoluble 9.06E-03 -7.64%

Lung FFTF 1 insoluble 5.24E-02 Mk 16 1 insoluble 3.43E-02 -34.65%

Colon FFTF 1 insoluble 5.06E-03 Mk 16 1 insoluble 4.18E-03 -17.36%

Esophagus FFTF 1 soluble 1.26E-03 Mk 16 1 soluble 4.92E-04 -60.95%

Gonads FFTF 1 soluble 1.38E-03 Mk 16 1 soluble 6.38E-04 -53.87%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 43 of 100

Table 2-23. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta air samples at 180 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 1.99E-03 Mk V-B soluble 8.98E-04 -54.79%

Urinary bladder FFTF 1 soluble 2.06E-03 Mk V-B soluble 7.14E-04 -65.29%

Brain FFTF 1 soluble 1.77E-03 Mk V-B soluble 6.68E-04 -62.23%

Breast FFTF 1 soluble 1.73E-03 Mk V-B soluble 6.12E-04 -64.62%

Gall bladder FFTF 1 soluble 1.96E-03 Mk 16 1 soluble 7.39E-04 -62.18%

Heart wall FFTF 1 soluble 1.91E-03 Mk 16 1 soluble 7.44E-04 -61.13%

Kidneys FFTF 1 soluble 1.91E-03 Mk V-B soluble 7.75E-04 -59.43%

Liver TRIGA 1 soluble 1.95E-02 Mk 16 1 soluble 1.94E-02 -0.34%

Muscle FFTF 1 soluble 1.82E-03 Mk V-B soluble 6.71E-04 -63.03%

Ovaries FFTF 1 soluble 1.95E-03 Mk V-B soluble 8.37E-04 -57.04%

Pancreas FFTF 1 soluble 1.95E-03 Mk 16 1 soluble 7.54E-04 -61.34%

Testes FFTF 1 soluble 1.77E-03 Mk 16 1 soluble 5.75E-04 -67.44%

Thyroid FFTF 1 soluble 1.82E-03 Mk 16 1 soluble 6.54E-04 -64.03%

Red bone marrow TRIGA 1 soluble 1.27E-02 Mk 16 1 soluble 7.45E-03 -41.49%

Bone surface TRIGA 1 soluble 3.17E-02 Mk 16 1 soluble 1.96E-02 -38.17%

Stomach FFTF 1 soluble 1.97E-03 Mk 16 1 soluble 7.98E-04 -59.56%

Small intestine FFTF 1 soluble 2.28E-03 Mk 16 1 soluble 1.16E-03 -49.31%

Upper large intestine FFTF 1 soluble 4.29E-03 Mk 16 1 soluble 3.19E-03 -25.67%

Lower large intestine FFTF 1 insoluble 1.00E-02 Mk 16 1 insoluble 8.23E-03 -17.85%

Skin FFTF 1 soluble 1.69E-03 Mk V-B soluble 5.72E-04 -66.22%

Spleen FFTF 1 soluble 1.86E-03 Mk 16 1 soluble 6.73E-04 -63.71%

Thymus FFTF 1 soluble 1.84E-03 Mk 16 1 soluble 6.82E-04 -62.93%

Uterus FFTF 1 soluble 1.91E-03 Mk 16 1 soluble 7.08E-04 -62.83%

Extrathoracic airways TRIGA 2 insoluble 1.10E-02 Mk V-B insoluble 1.08E-02 -1.94%

Lung FFTF 2 insoluble 7.18E-02 Mk 16 1 insoluble 5.23E-02 -27.16%

Colon FFTF 1 insoluble 6.49E-03 Mk 16 1 insoluble 5.26E-03 -18.84%

Esophagus FFTF 1 soluble 1.84E-03 Mk 16 1 soluble 6.82E-04 -62.93%

Gonads FFTF 1 soluble 1.95E-03 Mk V-B soluble 8.37E-04 -57.04%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 44 of 100

Table 2-24. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross beta air samples at 1 year decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 2.20E-03 Mk V-B soluble 8.84E-04 -59.79%

Urinary bladder FFTF 1 soluble 2.32E-03 Mk V-B soluble 8.40E-04 -63.85%

Brain FFTF 1 soluble 1.97E-03 Mk V-B soluble 7.56E-04 -61.68%

Breast FFTF 1 soluble 1.94E-03 Mk V-B soluble 7.40E-04 -61.86%

Gall bladder FFTF 1 soluble 2.22E-03 Mk V-B soluble 8.43E-04 -61.98%

Heart wall FFTF 1 soluble 2.15E-03 Mk V-B soluble 8.26E-04 -61.51%

Kidneys FFTF 1 soluble 2.13E-03 Mk V-B soluble 8.27E-04 -61.20%

Liver ATR 1 soluble 2.40E-02 Mk VI-B 2 soluble 2.40E-02 0.09%

Muscle FFTF 1 soluble 2.04E-03 Mk V-B soluble 7.73E-04 -62.04%

Ovaries FFTF 1 soluble 2.16E-03 Mk V-B soluble 8.46E-04 -60.82%

Pancreas FFTF 1 soluble 2.20E-03 Mk V-B soluble 8.34E-04 -62.00%

Testes FFTF 1 soluble 2.01E-03 Mk V-B soluble 7.25E-04 -63.90%

Thyroid FFTF 1 soluble 2.05E-03 Mk V-B soluble 7.64E-04 -62.71%

Red bone marrow TRIGA 1 soluble 1.67E-02 Mk 16 1 soluble 9.45E-03 -43.40%

Bone surface TRIGA 1 soluble 4.03E-02 Mk 16 1 soluble 2.18E-02 -45.96%

Stomach FFTF 1 soluble 2.21E-03 Mk V-B soluble 9.14E-04 -58.65%

Small intestine FFTF 1 soluble 2.50E-03 Mk V-B soluble 1.22E-03 -51.09%

Upper large intestine FFTF 1 soluble 4.51E-03 Mk V-B soluble 3.32E-03 -26.36%

Lower large intestine FFTF 2 insoluble 1.04E-02 Mk V-B insoluble 8.62E-03 -16.79%

Skin FFTF 1 soluble 1.90E-03 Mk V-B soluble 7.16E-04 -62.38%

Spleen FFTF 1 soluble 2.09E-03 Mk V-B soluble 7.81E-04 -62.66%

Thymus FFTF 1 soluble 2.07E-03 Mk V-B soluble 7.84E-04 -62.09%

Uterus FFTF 1 soluble 2.15E-03 Mk V-B soluble 7.98E-04 -62.83%

Extrathoracic airways TRIGA 1 insoluble 1.07E-02 Mk V-B insoluble 1.03E-02 -4.47%

Lung FFTF 2 insoluble 7.65E-02 Mk V-B insoluble 6.03E-02 -21.18%

Colon FFTF 1 insoluble 6.72E-03 Mk V-B insoluble 5.47E-03 -18.60%

Esophagus FFTF 1 soluble 2.07E-03 Mk V-B soluble 7.84E-04 -62.09%

Gonads FFTF 1 soluble 2.16E-03 Mk V-B soluble 8.46E-04 -60.82%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 45 of 100

Table 2-25. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma air samples at 10 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 1.42E-03 Mk 16 1 soluble 7.74E-04 -45.39%

Urinary bladder FFTF 1 soluble 2.59E-03 Mk V-B soluble 2.46E-03 -5.14%

Brain FFTF 1 soluble 1.38E-03 Mk 16 1 soluble 7.04E-04 -48.83%

Breast FFTF 1 soluble 1.16E-03 Mk 16 1 soluble 4.78E-04 -58.72%

Gall bladder FFTF 1 soluble 1.30E-03 Mk 16 1 soluble 5.60E-04 -56.75%

Heart wall FFTF 1 soluble 1.33E-03 Mk 16 1 soluble 6.22E-04 -53.37%

Kidneys FFTF 1 soluble 1.32E-03 Mk 16 1 soluble 6.43E-04 -51.31%

Liver TRIGA 1 soluble 1.50E-02 Mk 16 1 soluble 8.06E-03 -46.35%

Muscle FFTF 1 soluble 1.36E-03 Mk 16 1 soluble 6.62E-04 -51.32%

Ovaries FFTF 1 soluble 1.39E-03 Mk 16 1 soluble 7.07E-04 -49.10%

Pancreas FFTF 1 soluble 1.33E-03 Mk 16 1 soluble 6.11E-04 -53.99%

Testes FFTF 1 soluble 1.12E-03 Mk 16 1 soluble 4.00E-04 -64.30%

Thyroid ATR 2 soluble 1.22E+00 Mk V-B soluble 1.23E+00 1.00%

Red bone marrow TRIGA 1 soluble 9.46E-03 Mk 16 1 soluble 4.66E-03 -50.72%

Bone surface TRIGA 1 soluble 2.70E-02 Mk 16 1 soluble 1.54E-02 -42.85%

Stomach FFTF 1 soluble 1.43E-03 Mk 16 1 soluble 7.21E-04 -49.59%

Small intestine FFTF 1 soluble 1.88E-03 Mk 16 1 soluble 1.19E-03 -36.39%

Upper large intestine TRIGA 1 soluble 3.69E-03 Mk 16 1 soluble 2.75E-03 -25.52%

Lower large intestine TRIGA 1 insoluble 9.43E-03 Mk 16 1 insoluble 7.13E-03 -24.36%

Skin FFTF 1 soluble 1.15E-03 Mk 16 1 soluble 4.69E-04 -59.08%

Spleen FFTF 1 soluble 1.23E-03 Mk 16 1 soluble 5.19E-04 -57.91%

Thymus FFTF 1 soluble 1.41E-03 Mk 16 1 soluble 6.99E-04 -50.51%

Uterus FFTF 1 soluble 1.31E-03 Mk 16 1 soluble 5.89E-04 -55.10%

Extrathoracic airways TRIGA 1 insoluble 1.50E-02 Mk 16 1 insoluble 1.22E-02 -19.15%

Lung FFTF 1 insoluble 5.17E-02 Mk 16 1 insoluble 3.51E-02 -32.12%

Colon TRIGA 1 insoluble 6.09E-03 Mk 16 1 insoluble 4.60E-03 -24.56%

Esophagus FFTF 1 soluble 1.41E-03 Mk 16 1 soluble 6.99E-04 -50.51%

Gonads FFTF 1 soluble 1.39E-03 Mk 16 1 soluble 7.07E-04 -49.10%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 46 of 100

Table 2-26. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma air samples at 40 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 2.17E-03 Mk 16 1 soluble 1.07E-03 -50.95%

Urinary bladder FFTF 1 soluble 2.29E-03 Mk V-B soluble 9.97E-04 -56.52%

Brain FFTF 1 soluble 1.88E-03 Mk 16 1 soluble 7.50E-04 -60.13%

Breast FFTF 1 soluble 1.77E-03 Mk 16 1 soluble 6.19E-04 -65.06%

Gall bladder FFTF 1 soluble 2.02E-03 Mk 16 1 soluble 7.70E-04 -61.90%

Heart wall FFTF 1 soluble 2.01E-03 Mk 16 1 soluble 8.05E-04 -59.90%

Kidneys FFTF 1 soluble 2.03E-03 Mk 16 1 soluble 8.68E-04 -57.30%

Liver TRIGA 1 soluble 2.46E-02 Mk 16 1 soluble 1.39E-02 -43.40%

Muscle FFTF 1 soluble 1.91E-03 Mk 16 1 soluble 7.36E-04 -61.45%

Ovaries FFTF 1 soluble 2.12E-03 Mk 16 1 soluble 9.61E-04 -54.65%

Pancreas FFTF 1 soluble 2.05E-03 Mk 16 1 soluble 8.28E-04 -59.59%

Testes FFTF 1 soluble 1.77E-03 Mk 16 1 soluble 5.42E-04 -69.38%

Thyroid ATR 2 soluble 2.45E-01 Mk V-B soluble 2.39E-01 -2.37%

Red bone marrow TRIGA 1 soluble 1.51E-02 Mk 16 1 soluble 7.10E-03 -52.97%

Bone surface TRIGA 1 soluble 4.18E-02 Mk 16 1 soluble 2.30E-02 -45.00%

Stomach FFTF 1 soluble 2.07E-03 Mk 16 1 soluble 8.65E-04 -58.30%

Small intestine FFTF 1 soluble 2.55E-03 Mk 16 1 soluble 1.38E-03 -45.88%

Upper large intestine TRIGA 1 soluble 5.20E-03 Mk 16 1 soluble 3.77E-03 -27.50%

Lower large intestine TRIGA 1 insoluble 1.33E-02 Mk 16 1 insoluble 9.83E-03 -25.93%

Skin FFTF 1 soluble 1.73E-03 Mk 16 1 soluble 5.77E-04 -66.61%

Spleen FFTF 1 soluble 1.91E-03 Mk 16 1 soluble 7.01E-04 -63.38%

Thymus FFTF 1 soluble 1.93E-03 Mk 16 1 soluble 7.42E-04 -61.60%

Uterus FFTF 1 soluble 1.99E-03 Mk 16 1 soluble 7.69E-04 -61.44%

Extrathoracic airways TRIGA 1 insoluble 1.83E-02 Mk 16 1 insoluble 1.37E-02 -25.54%

Lung FFTF 1 insoluble 8.04E-02 Mk 16 1 insoluble 5.16E-02 -35.75%

Colon TRIGA 1 insoluble 8.55E-03 Mk 16 1 insoluble 6.30E-03 -26.37%

Esophagus FFTF 1 soluble 1.93E-03 Mk 16 1 soluble 7.42E-04 -61.60%

Gonads FFTF 1 soluble 2.12E-03 Mk 16 1 soluble 9.61E-04 -54.65%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 47 of 100

Table 2-27. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma air samples at 180 days decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 1 soluble 5.06E-03 Mk 16 1 soluble 1.86E-03 -63.21%

Urinary bladder FFTF 1 soluble 5.23E-03 Mk 16 1 soluble 1.51E-03 -71.18%

Brain FFTF 1 soluble 4.50E-03 Mk 16 1 soluble 1.38E-03 -69.22%

Breast FFTF 1 soluble 4.40E-03 Mk 16 1 soluble 1.30E-03 -70.55%

Gall bladder FFTF 1 soluble 4.98E-03 Mk 16 1 soluble 1.57E-03 -68.41%

Heart wall FFTF 1 soluble 4.87E-03 Mk 16 1 soluble 1.58E-03 -67.52%

Kidneys FFTF 1 soluble 4.86E-03 Mk 16 1 soluble 1.61E-03 -66.82%

Liver TRIGA 1 soluble 5.89E-02 Mk 16 1 soluble 4.13E-02 -29.88%

Muscle FFTF 1 soluble 4.62E-03 Mk 16 1 soluble 1.42E-03 -69.31%

Ovaries FFTF 1 soluble 4.96E-03 Mk 16 1 soluble 1.72E-03 -65.35%

Pancreas FFTF 1 soluble 4.96E-03 Mk 16 1 soluble 1.60E-03 -67.70%

Testes FFTF 1 soluble 4.49E-03 Mk 16 1 soluble 1.22E-03 -72.79%

Thyroid FFTF 1 soluble 4.63E-03 Mk 16 1 soluble 1.39E-03 -69.95%

Red bone marrow TRIGA 1 soluble 3.85E-02 Mk 16 1 soluble 1.58E-02 -58.83%

Bone surface TRIGA 1 soluble 9.57E-02 Mk 16 1 soluble 4.16E-02 -56.49%

Stomach FFTF 1 soluble 5.02E-03 Mk 16 1 soluble 1.70E-03 -66.22%

Small intestine FFTF 1 soluble 5.81E-03 Mk 16 1 soluble 2.46E-03 -57.65%

Upper large intestine FFTF 1 soluble 1.09E-02 Mk 16 1 soluble 6.78E-03 -37.90%

Lower large intestine FFTF 1 insoluble 2.55E-02 Mk 16 1 insoluble 1.75E-02 -31.37%

Skin FFTF 1 soluble 4.31E-03 Mk 16 1 soluble 1.21E-03 -71.84%

Spleen FFTF 1 soluble 4.72E-03 Mk 16 1 soluble 1.43E-03 -69.69%

Thymus FFTF 1 soluble 4.68E-03 Mk 16 1 soluble 1.45E-03 -69.03%

Uterus FFTF 1 soluble 4.85E-03 Mk 16 1 soluble 1.51E-03 -68.94%

Extrathoracic airways TRIGA 1 insoluble 3.28E-02 Mk 16 1 insoluble 2.26E-02 -30.91%

Lung FFTF 1 insoluble 1.83E-01 Mk 16 1 insoluble 1.11E-01 -39.11%

Colon FFTF 1 insoluble 1.65E-02 Mk 16 1 insoluble 1.12E-02 -32.20%

Esophagus FFTF 1 soluble 4.68E-03 Mk 16 1 soluble 1.45E-03 -69.03%

Gonads FFTF 1 soluble 4.96E-03 Mk 16 1 soluble 1.72E-03 -65.35%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 48 of 100

Table 2-28. Comparisons of organ dose results for the OTIB-0054 representative reactor cases and 

the SRS cases for gross gamma air samples at 1 year decay.

Organ

Limiting reactor and dose (rem)

Difference 

(SRS:rep.)

Representative reactors SRS cases

Limiting reactors 

and solubility Dose

Limiting reactors 

and solubility Dose

Adrenals FFTF 2 soluble 8.39E-03 Mk 16 1 soluble 3.94E-03 -53.07%

Urinary bladder FFTF 2 soluble 9.01E-03 Mk 16 1 soluble 3.68E-03 -59.14%

Brain FFTF 2 soluble 7.74E-03 Mk 16 1 soluble 3.23E-03 -58.28%

Breast FFTF 2 soluble 7.65E-03 Mk 16 1 soluble 3.15E-03 -58.75%

Gall bladder FFTF 2 soluble 8.41E-03 Mk 16 1 soluble 3.78E-03 -55.02%

Heart wall FFTF 2 soluble 8.23E-03 Mk 16 1 soluble 3.67E-03 -55.38%

Kidneys FFTF 2 soluble 8.19E-03 Mk 16 1 soluble 3.62E-03 -55.76%

Liver N Rx 2 soluble 1.18E-01 Mk 16 1 soluble 1.08E-01 -8.02%

Muscle FFTF 2 soluble 7.92E-03 Mk 16 1 soluble 3.36E-03 -57.51%

Ovaries FFTF 2 soluble 8.27E-03 Mk 16 1 soluble 3.72E-03 -54.99%

Pancreas FFTF 2 soluble 8.36E-03 Mk 16 1 soluble 3.74E-03 -55.23%

Testes FFTF 2 soluble 7.81E-03 Mk 16 1 soluble 3.21E-03 -58.91%

Thyroid FFTF 2 soluble 7.93E-03 Mk 16 1 soluble 3.37E-03 -57.45%

Red bone marrow TRIGA 1 soluble 7.63E-02 Mk 16 1 soluble 4.26E-02 -44.14%

Bone surface TRIGA 1 soluble 1.84E-01 Mk 16 1 soluble 9.82E-02 -46.67%

Stomach FFTF 2 soluble 8.61E-03 Mk 16 1 soluble 4.04E-03 -53.04%

Small intestine FFTF 2 soluble 9.81E-03 Mk 16 1 soluble 5.43E-03 -44.60%

Upper large intestine FFTF 2 soluble 1.87E-02 Mk 16 1 soluble 1.47E-02 -21.37%

Lower large intestine N Rx 2 insoluble 4.70E-02 Mk 16 1 insoluble 3.78E-02 -19.59%

Skin FFTF 2 soluble 7.55E-03 Mk 16 1 soluble 3.03E-03 -59.90%

Spleen FFTF 2 soluble 8.07E-03 Mk 16 1 soluble 3.47E-03 -56.93%

Thymus FFTF 2 soluble 7.99E-03 Mk 16 1 soluble 3.45E-03 -56.78%

Uterus FFTF 2 soluble 8.21E-03 Mk 16 1 soluble 3.60E-03 -56.19%

Extrathoracic airways N Rx 2 insoluble 5.27E-02 Mk 16 1 insoluble 4.51E-02 -14.50%

Lung FFTF 2 insoluble 3.27E-01 Mk 16 1 insoluble 2.60E-01 -20.60%

Colon N Rx 2 insoluble 3.00E-02 Mk 16 1 insoluble 2.42E-02 -19.34%

Esophagus FFTF 2 soluble 7.99E-03 Mk 16 1 soluble 3.45E-03 -56.78%

Gonads FFTF 2 soluble 8.27E-03 Mk 16 1 soluble 3.72E-03 -54.99%
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 49 of 100

Table 3-1. SRS-specific chemical yield 

values for processed urine samples.

Radionuclide Chemical yield

Sr-891

Sr-901

Y-901

Y-911

Zr-951

Nb-951

Mo-990

Ru-1030

Ru-1060

Te-129m0

Te-1320

I-1310

I-1320

Cs-1340

Cs-1370

Ba-1401

La-1401

Ce-1411

Ce-1441

Pr-1431

Pr-1441

Nd-1471

Pm-1471

Eu-1541

Eu-1551
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 50 of 100

Table 3-2. IRFs and yield and counting adjustment factors for beta and gamma counts.

Radionuclide

Absorption 

type

Beta 

Yield

Gamma 

Yield

IRF values

90 d 2 y 30 y

Sr-89/Y-89m F 1.0 0.000093 1.900E-01 1.915E-01 1.915E-01

Sr-90 F 1.0 0.0 2.130E-01 2.310E-01 2.490E-01

Y-90 S 1.0 0.0 3.392E-05 3.392E-05 3.392E-05

Y-91 S 1.0 0.003 7.370E-05 8.579E-05 8.579E-05

Zr-95 S 1.0 0.996 5.280E-04 5.805E-04 5.810E-04

Nb-95 S 0.0 0.998 1.930E-03 1.983E-03 1.980E-03

Ru-103 S 1.0 0.9306 1.040E-02 1.056E-02 1.060E-02

Ru-106/Rh-106 S 2.0 0.342 1.330E-02 1.559E-02 1.593E-02

Ba-140 F 1.0 0.404 2.422E-02 2.423E-02 2.423E-02

La-140 M 1.0 2.1542 4.780E-06 4.780E-06 4.780E-06

Ce-141 S 1.0 0.48 5.040E-07 6.472E-07 6.470E-07

Ce-144/Pr-144 S 1.98 0.134 1.120E-06 9.103E-06 1.284E-05

Pr-143 S 1.0 0.0 3.770E-05 3.770E-05 3.770E-05

Pr-144 S 1.0 0.0257 1.435E-09 1.435E-09 1.435E-09

Nd-147 S 1.0 0.2 2.810E-05 2.809E-05 2.810E-05

Pm-147 S 1.0 0.0 5.100E-05 1.884E-04 4.392E-04

Eu-154 M 1.0 1.633 4.605E-03 8.730E-03 1.756E-02

Eu-155 M 0.0 1.4468 4.568E-03 8.488E-03 1.409E-02

Table 3-3. SRS-specific urine activity fractions for 90Sr.

Nuclide and

intake duration

Fraction of beta activity in urine: Mk V-B Fraction of beta activity in urine: Mk 16 1 Fraction of beta activity in urine: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90, 90 days 1.29E-02 2.12E-02 1.19E-01 4.08E-01 3.43E-02 5.22E-02 2.23E-01 5.04E-01 2.51E-02 3.87E-02 1.83E-01 4.76E-01

Sr-90, 2 years 1.39E-02 2.27E-02 1.19E-01 4.16E-01 3.68E-02 5.57E-02 2.23E-01 5.09E-01 2.69E-02 4.14E-02 1.83E-01 4.82E-01

Sr-90, 30 years 1.50E-02 2.44E-02 1.33E-01 4.25E-01 3.94E-02 5.95E-02 2.41E-01 5.13E-01 2.88E-02 4.43E-02 2.00E-01 4.88E-01

Nuclide and 

intake duration

Fraction of beta activity in urine: Mk VI-B 1 Fraction of beta activity in urine: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-90, 90 days 2.75E-02 4.23E-02 1.94E-01 4.85E-01 2.75E-02 4.22E-02 1.94E-01 4.85E-01

Sr-90, 2 years 2.95E-02 4.52E-02 1.94E-01 4.91E-01 2.95E-02 4.52E-02 1.94E-01 4.91E-01

Sr-90, 30 years 3.16E-02 4.83E-02 2.12E-01 4.96E-01 3.16E-02 4.83E-02 2.12E-01 4.96E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 51 of 100

Table 3-4. SRS-specific urine activity fractions for 95Zr.

Nuclide and 

intake duration

Fraction of gamma activity in urine: Mk V-B Fraction of gamma activity in urine: Mk 16 1 Fraction of gamma activity in urine: Mk 16 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Zr-95, 90 days 1.70E-02 5.15E-02 1.42E-01 1.27E-01 3.49E-02 8.34E-02 1.36E-01 1.20E-01 3.18E-02 7.93E-02 1.37E-01 1.24E-01

Zr-95, 2 years 1.87E-02 5.59E-02 1.50E-01 1.33E-01 3.80E-02 8.95E-02 1.42E-01 1.21E-01 3.46E-02 8.52E-02 1.44E-01 1.28E-01

Zr-95, 30 years 1.87E-02 5.60E-02 1.49E-01 1.31E-01 3.80E-02 8.94E-02 1.40E-01 1.10E-01 3.46E-02 8.52E-02 1.43E-01 1.22E-01

Nuclide and 

intake duration

Fraction of gamma activity in urine: Mk VI-B 1 Fraction of gamma activity in urine: Mk VI-B 2

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Zr-95, 90 days 3.29E-02 8.08E-02 1.37E-01 1.22E-01 3.29E-02 8.08E-02 1.37E-01 1.23E-01

Zr-95, 2 years 3.59E-02 8.69E-02 1.43E-01 1.24E-01 3.58E-02 8.68E-02 1.43E-01 1.26E-01

Zr-95, 30 years 3.59E-02 8.68E-02 1.42E-01 1.17E-01 3.58E-02 8.68E-02 1.42E-01 1.20E-01

Table 3-5. Associated radionuclide activity fractions for assigning intakes relative to 95Zr.

Table 3-5 values: Mark V-B Table 3-5 values: Mark 16 1

Nuclide

Intake relative to Zr-95

Nuclide

Intake relative to Zr-95

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 7.93E-01 7.27E-01 4.86E-01 2.85E-01 Sr-89 7.29E-01 6.68E-01 4.46E-01 2.62E-01

Sr-90 7.25E-03 1.00E-02 4.52E-02 3.31E-01 Sr-90 1.72E-02 2.37E-02 1.07E-01 7.83E-01

Y-91 9.15E-01 8.87E-01 7.69E-01 6.37E-01 Y-91 9.03E-01 8.76E-01 7.60E-01 6.29E-01

Zr-95 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Zr-95 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Nb-95 5.11E-01 9.11E-01 1.84E+00 2.13E+00 Nb-95 1.03E+00 1.31E+00 1.95E+00 2.15E+00

Ru-103 8.03E-01 6.54E-01 2.52E-01 7.11E-02 Ru-103 4.75E-01 3.87E-01 1.49E-01 4.21E-02

Ru-106 3.55E-02 4.65E-02 1.63E-01 8.55E-01 Ru-106 2.97E-02 3.89E-02 1.36E-01 7.16E-01

I-131 3.14E+01 3.27E+00 8.53E-05 7.49E-11 I-131 1.15E+01 1.19E+00 3.11E-05 2.73E-11

Cs-134 7.51E-04 1.01E-03 4.05E-03 2.53E-02 Cs-134 1.61E-02 2.17E-02 8.67E-02 5.42E-01

Cs-137 8.16E-03 1.13E-02 5.08E-02 3.72E-01 Cs-137 1.74E-02 2.41E-02 1.09E-01 7.96E-01

Ce-141 1.34E+00 9.77E-01 2.25E-01 3.22E-02 Ce-141 8.63E-01 6.30E-01 1.45E-01 2.08E-02

Ce-144 2.45E-01 3.15E-01 1.02E+00 4.83E+00 Ce-144 4.41E-01 5.68E-01 1.84E+00 8.68E+00

Pr-143 1.60E+00 4.78E-01 1.71E-03 9.96E-07 Pr-143 6.92E-01 2.07E-01 7.39E-04 4.31E-07

Pm-147 2.56E-02 4.15E-02 1.76E-01 1.14E+00 Pm-147 4.83E-02 6.81E-02 2.82E-01 1.83E+00
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 52 of 100

Table 3-5 values: Mark 16 2 Table 3-5 values: Mark VI-B 1

Nuclide

Intake relative to Zr-95

Nuclide

Intake relative to Zr-95

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 7.59E-01 6.96E-01 4.65E-01 2.73E-01 Sr-89 7.51E-01 6.88E-01 4.60E-01 2.70E-01

Sr-90 1.29E-02 1.78E-02 8.02E-02 5.87E-01 Sr-90 1.40E-02 1.94E-02 8.73E-02 6.39E-01

Y-91 9.19E-01 8.91E-01 7.73E-01 6.40E-01 Y-91 9.15E-01 8.88E-01 7.70E-01 6.37E-01

Zr-95 1.00E+00 1.00E+00 1.00E+00 1.00E+00 Zr-95 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Nb-95 9.24E-01 1.23E+00 1.93E+00 2.15E+00 Nb-95 9.60E-01 1.25E+00 1.93E+00 2.15E+00

Ru-103 5.04E-01 4.11E-01 1.58E-01 4.46E-02 Ru-103 4.90E-01 3.99E-01 1.53E-01 4.34E-02

Ru-106 2.28E-02 2.98E-02 1.04E-01 5.48E-01 Ru-106 2.39E-02 3.13E-02 1.10E-01 5.76E-01

I-131 1.30E+01 1.35E+00 3.52E-05 3.09E-11 I-131 1.24E+01 1.29E+00 3.36E-05 2.95E-11

Cs-134 7.28E-03 9.80E-03 3.92E-02 2.45E-01 Cs-134 1.16E-02 1.57E-02 6.27E-02 3.92E-01

Cs-137 1.30E-02 1.80E-02 8.13E-02 5.95E-01 Cs-137 1.42E-02 1.96E-02 8.84E-02 6.47E-01

Ce-141 9.47E-01 6.92E-01 1.59E-01 2.28E-02 Ce-141 9.17E-01 6.69E-01 1.54E-01 2.21E-02

Ce-144 3.61E-01 4.64E-01 1.50E+00 7.10E+00 Ce-144 3.83E-01 4.93E-01 1.60E+00 7.54E+00

Pr-143 7.88E-01 2.36E-01 8.41E-04 4.91E-07 Pr-143 7.52E-01 2.25E-01 8.03E-04 4.69E-07

Pm-147 4.08E-02 5.84E-02 2.43E-01 1.57E+00 Pm-147 4.03E-02 5.76E-02 2.39E-01 1.55E+00

Table 3-5 values: Mark VI-B 2

Nuclide

Intake relative to Zr-95

10 d 40 d 180 d 1 y

Sr-89 7.51E-01 6.89E-01 4.60E-01 2.70E-01

Sr-90 1.40E-02 1.94E-02 8.73E-02 6.39E-01

Y-91 9.15E-01 8.88E-01 7.70E-01 6.37E-01

Zr-95 1.00E+00 1.00E+00 1.00E+00 1.00E+00

Nb-95 9.60E-01 1.25E+00 1.93E+00 2.15E+00

Ru-103 4.89E-01 3.98E-01 1.53E-01 4.33E-02

Ru-106 2.37E-02 3.10E-02 1.09E-01 5.70E-01

I-131 1.24E+01 1.29E+00 3.36E-05 2.95E-11

Cs-134 9.42E-03 1.27E-02 5.07E-02 3.17E-01

Cs-137 1.42E-02 1.96E-02 8.83E-02 6.47E-01

Ce-141 9.19E-01 6.70E-01 1.54E-01 2.21E-02

Ce-144 3.83E-01 4.92E-01 1.59E+00 7.54E+00

Pr-143 7.55E-01 2.26E-01 8.07E-04 4.71E-07

Pm-147 4.25E-02 6.06E-02 2.51E-01 1.63E+00
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 53 of 100

Table 4-1. SRS-specific committed organ doses for 1 Bq/d in urine by gross beta at 10 days decay.

Organ

Limiting case and dose (mSv) for 1 Bq beta in urine

90-day chronic intake 30-year chronic intake

Limiting case

and solubility Dose

Limiting case

and solubility Dose

Adrenals Mk 16 1 soluble 4.57E-05 Mk 16 1 soluble 4.49E-05

Urinary bladder Mk V-B soluble 2.06E-04 Mk V-B soluble 2.04E-04

Bone surface Mk 16 1 soluble 9.35E-04 Mk 16 1 soluble 9.18E-04

Brain Mk V-B soluble 5.69E-05 Mk V-B soluble 5.63E-05

Breast Mk V-B soluble 3.21E-05 Mk V-B soluble 3.18E-05

Esophagus Mk V-B soluble 5.73E-05 Mk V-B soluble 5.67E-05

Stomach Mk V-B soluble 5.20E-05 Mk V-B soluble 5.15E-05

Small intestine Mk 16 1 soluble 5.89E-05 Mk 16 1 soluble 5.79E-05

Upper large intestine Mk 16 1 soluble 1.66E-04 Mk 16 1 soluble 1.63E-04

Lower large intestine Mk 16 1 insoluble 4.31E-04 Mk 16 1 insoluble 4.23E-04

Colon Mk 16 1 insoluble 2.79E-04 Mk 16 1 insoluble 2.74E-04

Kidneys Mk V-B soluble 3.87E-05 Mk V-B soluble 3.83E-05

Liver Mk 16 1 soluble 4.83E-04 Mk 16 1 soluble 4.75E-04

Muscle Mk V-B soluble 5.27E-05 Mk V-B soluble 5.22E-05

Ovaries Mk 16 1 soluble 4.18E-05 Mk 16 1 soluble 4.11E-05

Pancreas Mk V-B soluble 3.76E-05 Mk V-B soluble 3.72E-05

Red marrow Mk 16 1 soluble 2.80E-04 Mk 16 1 soluble 2.75E-04

Extrathoracic airways Mk V-B insoluble 9.36E-04 Mk V-B insoluble 9.27E-04

Lungs Mk 16 1 insoluble 2.13E-03 Mk 16 1 insoluble 2.09E-03

Skin Mk V-B soluble 3.37E-05 Mk V-B soluble 3.33E-05

Spleen Mk V-B soluble 3.25E-05 Mk V-B soluble 3.22E-05

Testes Mk V-B soluble 2.53E-05 Mk V-B soluble 2.50E-05

Thymus Mk V-B soluble 5.73E-05 Mk V-B soluble 5.67E-05

Thyroid Mk V-B soluble 1.03E-01 Mk V-B soluble 1.01E-01

Uterus Mk V-B soluble 3.66E-05 Mk V-B soluble 3.62E-05
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 54 of 100

Table 4-2. SRS-specific committed organ doses for 1 Bq/d in urine by gross beta at 180 days decay.

Organ

Limiting case and dose (mSv) for 1 Bq beta in urine

90-day chronic intake 30-year chronic intake

Limiting case 

and solubility Dose

Limiting case 

And solubility Dose

Adrenals Mk 16 1 soluble 8.46E-05 Mk 16 1 soluble 7.83E-05

Urinary bladder Mk 16 1 soluble 6.92E-05 Mk 16 1 soluble 6.40E-05

Bone surface Mk 16 1 soluble 1.93E-03 Mk 16 1 soluble 1.78E-03

Brain Mk 16 1 soluble 6.38E-05 Mk 16 1 soluble 5.90E-05

Breast Mk 16 1 soluble 6.08E-05 Mk 16 1 soluble 5.62E-05

Esophagus Mk 16 1 soluble 6.73E-05 Mk 16 1 soluble 6.22E-05

Stomach Mk 16 1 soluble 7.86E-05 Mk 16 1 soluble 7.27E-05

Small intestine Mk 16 1 soluble 1.14E-04 Mk 16 1 soluble 1.05E-04

Upper large intestine Mk 16 1 soluble 3.17E-04 Mk 16 1 soluble 2.93E-04

Lower large intestine Mk 16 1 insoluble 8.10E-04 Mk 16 1 insoluble 7.49E-04

Colon Mk 16 1 insoluble 5.23E-04 Mk 16 1 insoluble 4.84E-04

Kidneys Mk 16 1 soluble 7.39E-05 Mk 16 1 soluble 6.84E-05

Liver Mk 16 1 soluble 1.90E-03 Mk 16 1 soluble 1.76E-03

Muscle Mk 16 1 soluble 6.43E-05 Mk 16 1 soluble 5.95E-05

Ovaries Mk 16 1 soluble 7.96E-05 Mk 16 1 soluble 7.37E-05

Pancreas Mk 16 1 soluble 7.49E-05 Mk 16 1 soluble 6.93E-05

Red marrow Mk 16 1 soluble 7.26E-04 Mk 16 1 soluble 6.72E-04

Extrathoracic airways Mk 16 1 insoluble 1.04E-03 Mk 16 1 insoluble 9.65E-04

Lungs Mk 16 1 insoluble 5.18E-03 Mk 16 1 insoluble 4.80E-03

Skin Mk 16 1 soluble 5.59E-05 Mk 16 1 soluble 5.17E-05

Spleen Mk 16 1 soluble 6.73E-05 Mk 16 1 soluble 6.22E-05

Testes Mk 16 1 soluble 5.64E-05 Mk 16 1 soluble 5.22E-05

Thymus Mk 16 1 soluble 6.73E-05 Mk 16 1 soluble 6.22E-05

Thyroid Mk 16 1 soluble 6.45E-05 Mk 16 1 soluble 5.96E-05

Uterus Mk 16 1 soluble 6.82E-05 Mk 16 1 soluble 6.31E-05
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 55 of 100

Table 4-3. SRS-specific committed organ doses for 1 Bq/d in urine by gross beta at 1 year decay.

Organ

Limiting case and dose (mSv) for 1 Bq beta in urine

90-day chronic intake 30-year chronic intake

Limiting case 

and solubility Dose

Limiting case 

and solubility Dose

Adrenals Mk V-B soluble 1.17E-04 Mk V-B soluble 1.05E-04

Urinary bladder Mk V-B soluble 1.11E-04 Mk V-B soluble 9.86E-05

Bone surface Mk V-B soluble 2.61E-03 Mk V-B soluble 2.33E-03

Brain Mk V-B soluble 9.98E-05 Mk V-B soluble 8.90E-05

Breast Mk V-B soluble 9.92E-05 Mk V-B soluble 8.85E-05

Esophagus Mk V-B soluble 1.05E-04 Mk V-B soluble 9.33E-05

Stomach Mk V-B soluble 1.21E-04 Mk V-B soluble 1.08E-04

Small intestine Mk V-B soluble 1.62E-04 Mk V-B soluble 1.44E-04

Upper large intestine Mk V-B soluble 4.43E-04 Mk V-B soluble 3.95E-04

Lower large intestine Mk V-B insoluble 1.14E-03 Mk V-B insoluble 1.02E-03

Colon Mk V-B insoluble 7.34E-04 Mk V-B insoluble 6.55E-04

Kidneys Mk V-B soluble 1.09E-04 Mk V-B soluble 9.69E-05

Liver Mk V-B soluble 2.97E-03 Mk V-B soluble 2.65E-03

Muscle Mk V-B soluble 1.01E-04 Mk V-B soluble 8.98E-05

Ovaries Mk V-B soluble 1.13E-04 Mk V-B soluble 1.01E-04

Pancreas Mk V-B soluble 1.12E-04 Mk V-B soluble 9.96E-05

Red marrow Mk 16 1 soluble 1.08E-03 Mk V-B soluble 9.57E-04

Extrathoracic airways Mk V-B insoluble 1.35E-03 Mk V-B insoluble 1.21E-03

Lungs Mk V-B insoluble 8.05E-03 Mk V-B insoluble 7.18E-03

Skin Mk V-B soluble 9.44E-05 Mk V-B soluble 8.42E-05

Spleen Mk V-B soluble 1.05E-04 Mk V-B soluble 9.33E-05

Testes Mk V-B soluble 9.55E-05 Mk V-B soluble 8.52E-05

Thymus Mk V-B soluble 1.05E-04 Mk V-B soluble 9.33E-05

Thyroid Mk V-B soluble 1.01E-04 Mk V-B soluble 9.00E-05

Uterus Mk V-B soluble 1.04E-04 Mk V-B soluble 9.30E-05
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 56 of 100

Table 4-4. Associated radionuclide activity fractions for assigning intakes, particulates only (no 131I).

Radionuclide

Mk V-B base Mk 16 base Mk 16 A1

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 1.09E-01 1.20E-01 8.05E-02 2.43E-02 1.16E-01 1.15E-01 6.37E-02 1.50E-02 1.21E-01 1.21E-01 7.12E-02 1.84E-02

Sr-90 9.96E-04 1.65E-03 7.49E-03 2.82E-02 2.74E-03 4.07E-03 1.53E-02 4.48E-02 2.04E-03 3.09E-03 1.23E-02 3.97E-02

Y-91 1.26E-01 1.46E-01 1.28E-01 5.44E-02 1.44E-01 1.51E-01 1.08E-01 3.60E-02 1.46E-01 1.55E-01 1.18E-01 4.33E-02

Zr-95 1.37E-01 1.65E-01 1.66E-01 8.54E-02 1.60E-01 1.72E-01 1.43E-01 5.73E-02 1.59E-01 1.74E-01 1.53E-01 6.77E-02

Nb-95 7.02E-02 1.50E-01 3.04E-01 1.82E-01 1.64E-01 2.24E-01 2.78E-01 1.23E-01 1.47E-01 2.13E-01 2.95E-01 1.45E-01

Ru-103 1.10E-01 1.08E-01 4.17E-02 6.07E-03 7.59E-02 6.65E-02 2.12E-02 2.41E-03 8.00E-02 7.14E-02 2.42E-02 3.02E-03

Ru-106 4.88E-03 7.67E-03 2.70E-02 7.30E-02 4.75E-03 6.69E-03 1.95E-02 4.10E-02 3.62E-03 5.18E-03 1.60E-02 3.71E-02

Cs-134 1.03E-04 1.67E-04 6.71E-04 2.16E-03 2.57E-03 3.72E-03 1.24E-02 3.10E-02 1.16E-03 1.70E-03 6.00E-03 1.66E-02

Cs-137 1.12E-03 1.86E-03 8.43E-03 3.18E-02 2.79E-03 4.14E-03 1.55E-02 4.56E-02 2.07E-03 3.13E-03 1.24E-02 4.03E-02

Ce-141 1.84E-01 1.61E-01 3.73E-02 2.75E-03 1.38E-01 1.08E-01 2.07E-02 1.19E-03 1.50E-01 1.20E-01 2.43E-02 1.54E-03

Ce-144 3.37E-02 5.20E-02 1.69E-01 4.12E-01 7.05E-02 9.75E-02 2.62E-01 4.97E-01 5.73E-02 8.07E-02 2.30E-01 4.80E-01

Pr-143 2.19E-01 7.89E-02 2.83E-04 8.50E-08 1.11E-01 3.56E-02 1.05E-04 2.47E-08 1.25E-01 4.10E-02 1.29E-04 3.32E-08

Pm-147 3.51E-03 6.85E-03 2.92E-02 9.74E-02 7.71E-03 1.17E-02 4.03E-02 1.05E-01 6.48E-03 1.02E-02 3.72E-02 1.06E-01

Radionuclide

Mk VI-B base Mk VI-B A1

10 d 40 d 180 d 1 y 10 d 40 d 180 d 1 y

Sr-89 1.20E-01 1.20E-01 6.91E-02 1.74E-02 1.20E-01 1.20E-01 6.91E-02 1.74E-02

Sr-90 2.23E-03 3.36E-03 1.31E-02 4.13E-02 2.23E-03 3.36E-03 1.31E-02 4.13E-02

Y-91 1.46E-01 1.54E-01 1.16E-01 4.12E-02 1.46E-01 1.54E-01 1.16E-01 4.12E-02

Zr-95 1.59E-01 1.74E-01 1.50E-01 6.46E-02 1.59E-01 1.74E-01 1.50E-01 6.47E-02

Nb-95 1.53E-01 2.18E-01 2.91E-01 1.39E-01 1.53E-01 2.18E-01 2.91E-01 1.39E-01

Ru-103 7.81E-02 6.93E-02 2.31E-02 2.80E-03 7.79E-02 6.91E-02 2.30E-02 2.80E-03

Ru-106 3.81E-03 5.43E-03 1.65E-02 3.72E-02 3.77E-03 5.38E-03 1.63E-02 3.68E-02

Cs-134 1.85E-03 2.72E-03 9.42E-03 2.53E-02 1.50E-03 2.20E-03 7.63E-03 2.05E-02

Cs-137 2.26E-03 3.40E-03 1.33E-02 4.19E-02 2.26E-03 3.40E-03 1.33E-02 4.18E-02

Ce-141 1.46E-01 1.16E-01 2.31E-02 1.43E-03 1.46E-01 1.16E-01 2.32E-02 1.43E-03

Ce-144 6.10E-02 8.55E-02 2.40E-01 4.87E-01 6.10E-02 8.55E-02 2.40E-01 4.87E-01

Pr-143 1.20E-01 3.91E-02 1.21E-04 3.03E-08 1.20E-01 3.92E-02 1.21E-04 3.04E-08

Pm-147 6.43E-03 1.00E-02 3.59E-02 1.00E-01 6.77E-03 1.05E-02 3.78E-02 1.05E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 57 of 100

Table 4-5. Committed organ doses for a 4,400 dpm/d chronic intake rate at 10 days decay.

Organ

Limiting case and dose (mSv) for a 4,400 dpm/d intake rate

90-day chronic intake 30-year chronic intake

Limiting case and solubility Dose Limiting case and solubility Dose

Adrenals Mk 16 1 soluble 5.13E-03 Mk 16 1 soluble 6.25E-01

Urinary bladder Mk V-B soluble 2.23E-02 Mk V-B soluble 2.71E+00

Bone surface Mk 16 1 soluble 1.05E-01 Mk 16 1 soluble 1.28E+01

Brain Mk V-B soluble 6.16E-03 Mk V-B soluble 7.50E-01

Breast Mk V-B soluble 3.47E-03 Mk V-B soluble 4.23E-01

Esophagus Mk V-B soluble 6.20E-03 Mk V-B soluble 7.55E-01

Stomach Mk V-B soluble 5.63E-03 Mk V-B soluble 6.86E-01

Small intestine Mk 16 1 soluble 6.62E-03 Mk 16 1 soluble 8.06E-01

Upper large intestine Mk 16 1 soluble 1.87E-02 Mk 16 1 soluble 2.27E+00

Lower large intestine Mk 16 1 insoluble 4.84E-02 Mk 16 1 insoluble 5.89E+00

Colon Mk 16 1 insoluble 3.14E-02 Mk 16 1 insoluble 3.82E+00

Kidneys Mk 16 1 soluble 4.28E-03 Mk 16 1 soluble 5.21E-01

Liver Mk 16 1 soluble 5.43E-02 Mk 16 1 soluble 6.61E+00

Muscle Mk V-B soluble 5.71E-03 Mk V-B soluble 6.95E-01

Ovaries Mk 16 1 soluble 4.70E-03 Mk 16 1 soluble 5.72E-01

Pancreas Mk 16 1 soluble 4.16E-03 Mk 16 1 soluble 5.07E-01

Red marrow Mk 16 1 soluble 3.14E-02 Mk 16 1 soluble 3.83E+00

Extrathoracic airways Mk V-B insoluble 1.01E-01 Mk V-B insoluble 1.23E+01

Lungs Mk 16 1 insoluble 2.39E-01 Mk 16 1 insoluble 2.91E+01

Skin Mk V-B soluble 3.64E-03 Mk V-B soluble 4.44E-01

Spleen Mk 16 1 soluble 3.56E-03 Mk 16 1 soluble 4.33E-01

Testes Mk V-B soluble 2.73E-03 Mk V-B soluble 3.33E-01

Thymus Mk V-B soluble 6.20E-03 Mk V-B soluble 7.55E-01

Thyroid Mk V-B soluble 1.11E+01 Mk V-B soluble 1.35E+03

Uterus Mk V-B soluble 3.96E-03 Mk V-B soluble 4.82E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 58 of 100

Table 4-6. Committed organ doses for a 4,400 dpm/d chronic intake rate at 180 days decay.

Organ

Limiting case and dose (mSv) for a 4,400 dpm/d intake rate

90-day chronic intake 30-year chronic intake

Limiting case and solubility Dose Limiting case and solubility Dose

Adrenals Mk 16 1 Soluble 8.16E-03 Mk 16 1 Soluble 9.93E-01

Urinary bladder Mk 16 1 Soluble 6.67E-03 Mk 16 1 Soluble 8.12E-01

Bone surface Mk 16 1 Soluble 1.86E-01 Mk 16 1 Soluble 2.26E+01

Brain Mk 16 1 Soluble 6.15E-03 Mk 16 1 Soluble 7.49E-01

Breast Mk 16 1 Soluble 5.86E-03 Mk 16 1 Soluble 7.13E-01

Esophagus Mk 16 1 Soluble 6.49E-03 Mk 16 1 Soluble 7.90E-01

Stomach Mk 16 1 Soluble 7.58E-03 Mk 16 1 Soluble 9.22E-01

Small intestine Mk 16 1 Soluble 1.10E-02 Mk 16 1 Soluble 1.34E+00

Upper large intestine Mk 16 1 Soluble 3.05E-02 Mk 16 1 Soluble 3.72E+00

Lower large intestine Mk 16 1 Insoluble 7.81E-02 Mk 16 1 Insoluble 9.51E+00

Colon Mk 16 1 Insoluble 5.04E-02 Mk 16 1 Insoluble 6.14E+00

Kidneys Mk 16 1 Soluble 7.12E-03 Mk 16 1 Soluble 8.67E-01

Liver Mk 16 1 Soluble 1.83E-01 Mk 16 1 Soluble 2.23E+01

Muscle Mk 16 1 Soluble 6.20E-03 Mk 16 1 Soluble 7.55E-01

Ovaries Mk 16 1 Soluble 7.68E-03 Mk 16 1 Soluble 9.35E-01

Pancreas Mk 16 1 Soluble 7.22E-03 Mk 16 1 Soluble 8.79E-01

Red marrow Mk 16 1 Soluble 7.00E-02 Mk 16 1 Soluble 8.52E+00

Extrathoracic airways Mk 16 1 Insoluble 1.01E-01 Mk 16 1 Insoluble 1.22E+01

Lungs Mk 16 1 Insoluble 5.00E-01 Mk 16 1 Insoluble 6.09E+01

Skin Mk 16 1 Soluble 5.39E-03 Mk 16 1 Soluble 6.56E-01

Spleen Mk 16 1 Soluble 6.49E-03 Mk 16 1 Soluble 7.90E-01

Testes Mk 16 1 Soluble 5.44E-03 Mk 16 1 Soluble 6.63E-01

Thymus Mk 16 1 Soluble 6.49E-03 Mk 16 1 Soluble 7.90E-01

Thyroid Mk 16 1 Soluble 6.22E-03 Mk 16 1 Soluble 7.57E-01

Uterus Mk 16 1 Soluble 6.58E-03 Mk 16 1 Soluble 8.01E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 59 of 100

Table 4-7. Committed organ doses for a 4,400 dpm/d chronic intake rate at 1 year decay.

Organ

Limiting case and dose (mSv) for a 4,400 dpm/d intake rate

90-day chronic intake 30-year chronic intake

Limiting case and solubility Dose Limiting case and solubility Dose

Adrenals Mk 16 1 soluble 1.24E-02 Mk 16 1 soluble 1.51E+00

Urinary bladder Mk 16 1 soluble 1.17E-02 Mk 16 1 soluble 1.43E+00

Bone surface Mk 16 1 soluble 3.15E-01 Mk 16 1 soluble 3.83E+01

Brain Mk 16 1 soluble 1.03E-02 Mk 16 1 soluble 1.26E+00

Breast Mk 16 1 soluble 1.03E-02 Mk 16 1 soluble 1.25E+00

Esophagus Mk 16 1 soluble 1.12E-02 Mk 16 1 soluble 1.36E+00

Stomach Mk 16 1 soluble 1.30E-02 Mk 16 1 soluble 1.58E+00

Small intestine Mk 16 1 soluble 1.73E-02 Mk 16 1 soluble 2.11E+00

Upper large intestine Mk 16 1 soluble 4.78E-02 Mk 16 1 soluble 5.82E+00

Lower large intestine Mk 16 1 insoluble 1.22E-01 Mk 16 1 insoluble 1.48E+01

Colon Mk 16 1 insoluble 7.87E-02 Mk 16 1 insoluble 9.58E+00

Kidneys Mk 16 1 soluble 1.16E-02 Mk 16 1 soluble 1.41E+00

Liver Mk 16 1 soluble 3.46E-01 Mk 16 1 soluble 4.21E+01

Muscle Mk 16 1 soluble 1.06E-02 Mk 16 1 soluble 1.29E+00

Ovaries Mk 16 1 soluble 1.20E-02 Mk 16 1 soluble 1.46E+00

Pancreas Mk 16 1 soluble 1.21E-02 Mk 16 1 soluble 1.47E+00

Red marrow Mk 16 1 soluble 1.35E-01 Mk 16 1 soluble 1.65E+01

Extrathoracic airways Mk 16 1 insoluble 1.44E-01 Mk 16 1 insoluble 1.76E+01

Lungs Mk 16 1 insoluble 8.42E-01 Mk 16 1 insoluble 1.02E+02

Skin Mk 16 1 soluble 9.67E-03 Mk 16 1 soluble 1.18E+00

Spleen Mk 16 1 soluble 1.13E-02 Mk 16 1 soluble 1.37E+00

Testes Mk 16 1 soluble 1.03E-02 Mk 16 1 soluble 1.25E+00

Thymus Mk 16 1 soluble 1.12E-02 Mk 16 1 soluble 1.36E+00

Thyroid Mk 16 1 soluble 1.08E-02 Mk 16 1 soluble 1.31E+00

Uterus Mk 16 1 soluble 1.13E-02 Mk 16 1 soluble 1.37E+00
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 60 of 100

Table 5-1. Comparisons of committed organ doses computed using the SRS Site Profile assumptions with those 

determined using the OTIB-0054 method for 1 Bq/d in urine by gross beta at 10 days decay.

Organ

Committed organ dose (mSv)

90-day intake period 30-year intake period

TBD 1 TBD 2 TBD 3 This report TBD 1 TBD 2 TBD 3 This report

Adrenals 1.39E-02 4.57E-05 1.45E+00 4.49E-05

Urinary bladder 1.59E-02 2.06E-04 1.66E+00 2.04E-04

Bone surface 2.08E-01 9.35E-04 2.17E+01 9.18E-04

Brain 1.32E-02 5.69E-05 1.38E+00 5.63E-05

Breast 1.30E-02 3.21E-05 1.35E+00 3.18E-05

Esophagus 1.36E-02 5.73E-05 1.42E+00 5.67E-05

Stomach 7.58E+00 5.20E-05 1.36E+02 5.15E-05

Small intestine 1.05E+01 5.89E-05 1.89E+02 5.79E-05

Upper large intestine 3.80E+01 1.66E-04 6.83E+02 1.63E-04

Lower large intestine 9.76E+01 4.31E-04 1.75E+03 4.23E-04

Colon 6.47E+01 2.79E-04 1.16E+03 2.74E-04

Kidneys 1.37E-02 3.87E-05 1.43E+00 3.83E-05

Liver 1.71E+02 4.83E-04 3.07E+03 4.75E-04

Muscle 1.35E-02 5.27E-05 1.41E+00 5.22E-05

Ovaries 1.40E-02 4.18E-05 1.46E+00 4.11E-05

Pancreas 1.40E-02 3.76E-05 1.46E+00 3.72E-05

Red marrow 9.78E-02 2.80E-04 1.02E+01 2.75E-04

Extrathoracic airways 6.40E+01 9.36E-04 1.15E+03 9.27E-04

Lungs 5.63E+02 2.13E-03 1.01E+04 2.09E-03

Skin 1.29E-02 3.37E-05 1.34E+00 3.33E-05

Spleen 1.37E-02 3.25E-05 1.43E+00 3.22E-05

Testes 1.34E-02 2.53E-05 1.39E+00 2.50E-05

Thymus 1.36E-02 5.73E-05 1.42E+00 5.67E-05

Thyroid 1.36E-02 1.03E-01 1.42E+00 1.01E-01

Uterus 1.40E-02 3.66E-05 1.46E+00 3.62E-05
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 61 of 100

Table 5-2. Comparisons of committed organ doses computed using the SRS Site Profile assumptions with those 

determined using the OTIB-0054 method for 1 Bq/d in urine by gross beta at 180 days decay.

Organ

Committed organ dose (mSv)

90-day intake period 30-year intake period

TBD 1 TBD 2 TBD 3 This report TBD 1 TBD 2 TBD 3 This report

Adrenals 1.39E-02 8.46E-05 1.45E+00 7.83E-05

Urinary bladder 1.59E-02 6.92E-05 1.66E+00 6.40E-05

Bone surface 2.08E-01 1.93E-03 2.17E+01 1.78E-03

Brain 1.32E-02 6.38E-05 1.38E+00 5.90E-05

Breast 1.30E-02 6.08E-05 1.35E+00 5.62E-05

Esophagus 1.36E-02 6.73E-05 1.42E+00 6.22E-05

Stomach 7.58E+00 7.86E-05 1.36E+02 7.27E-05

Small intestine 1.05E+01 1.14E-04 1.89E+02 1.05E-04

Upper large intestine 3.80E+01 3.17E-04 6.83E+02 2.93E-04

Lower large intestine 9.76E+01 8.10E-04 1.75E+03 7.49E-04

Colon 6.47E+01 5.23E-04 1.16E+03 4.84E-04

Kidneys 1.37E-02 7.39E-05 1.43E+00 6.84E-05

Liver 1.71E+02 1.90E-03 3.07E+03 1.76E-03

Muscle 1.35E-02 6.43E-05 1.41E+00 5.95E-05

Ovaries 1.40E-02 7.96E-05 1.46E+00 7.37E-05

Pancreas 1.40E-02 7.49E-05 1.46E+00 6.93E-05

Red marrow 9.78E-02 7.26E-04 1.02E+01 6.72E-04

Extrathoracic airways 6.40E+01 1.04E-03 1.15E+03 9.65E-04

Lungs 5.63E+02 5.18E-03 1.01E+04 4.80E-03

Skin 1.29E-02 5.59E-05 1.34E+00 5.17E-05

Spleen 1.37E-02 6.73E-05 1.43E+00 6.22E-05

Testes 1.34E-02 5.64E-05 1.39E+00 5.22E-05

Thymus 1.36E-02 6.73E-05 1.42E+00 6.22E-05

Thyroid 1.36E-02 6.45E-05 1.42E+00 5.96E-05

Uterus 1.40E-02 6.82E-05 1.46E+00 6.31E-05
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 62 of 100

Table 5-3. Comparisons of committed organ doses computed using the SRS Site Profile assumptions with those 

determined using the OTIB-0054 method for 1 Bq/d in urine by gross beta at 1 year decay.

Organ

Committed organ dose (mSv)

90-day intake period 30-year intake period

TBD 1 TBD 2 TBD 3 This report TBD 1 TBD 2 TBD 3 This report

Adrenals 1.39E-02 1.17E-04 1.45E+00 1.05E-04

Urinary bladder 1.59E-02 1.11E-04 1.66E+00 9.86E-05

Bone surface 2.08E-01 2.61E-03 2.17E+01 2.33E-03

Brain 1.32E-02 9.98E-05 1.38E+00 8.90E-05

Breast 1.30E-02 9.92E-05 1.35E+00 8.85E-05

Esophagus 1.36E-02 1.05E-04 1.42E+00 9.33E-05

Stomach 7.58E+00 1.21E-04 1.36E+02 1.08E-04

Small intestine 1.05E+01 1.62E-04 1.89E+02 1.44E-04

Upper large intestine 3.80E+01 4.43E-04 6.83E+02 3.95E-04

Lower large intestine 9.76E+01 1.14E-03 1.75E+03 1.02E-03

Colon 6.47E+01 7.34E-04 1.16E+03 6.55E-04

Kidneys 1.37E-02 1.09E-04 1.43E+00 9.69E-05

Liver 1.71E+02 2.97E-03 3.07E+03 2.65E-03

Muscle 1.35E-02 1.01E-04 1.41E+00 8.98E-05

Ovaries 1.40E-02 1.13E-04 1.46E+00 1.01E-04

Pancreas 1.40E-02 1.12E-04 1.46E+00 9.96E-05

Red marrow 9.78E-02 1.08E-03 1.02E+01 9.57E-04

Extrathoracic airways 6.40E+01 1.35E-03 1.15E+03 1.21E-03

Lungs 5.63E+02 8.05E-03 1.01E+04 7.18E-03

Skin 1.29E-02 9.44E-05 1.34E+00 8.42E-05

Spleen 1.37E-02 1.05E-04 1.43E+00 9.33E-05

Testes 1.34E-02 9.55E-05 1.39E+00 8.52E-05

Thymus 1.36E-02 1.05E-04 1.42E+00 9.33E-05

Thyroid 1.36E-02 1.01E-04 1.42E+00 9.00E-05

Uterus 1.40E-02 1.04E-04 1.46E+00 9.30E-05
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 63 of 100

Table 5-4. Comparisons of committed organ doses computed using the 

SRS Site Profile assumptions with those determined using the OTIB-0054 

method for a 4,400 dpm/d chronic intake rate at 10 days decay.

Organ

Committed organ dose (mSv)

90-day intake period 30-year intake period

TBD This report TBD This report

Adrenals 4.92E-02 5.13E-03 5.99E+00 6.25E-01

Urinary bladder 4.40E-02 2.23E-02 5.36E+00 2.71E+00

Bone surface 1.58E+00 1.05E-01 1.92E+02 1.28E+01

Brain 3.75E-02 6.16E-03 4.56E+00 7.50E-01

Breast 4.74E-02 3.47E-03 5.77E+00 4.23E-01

Esophagus 5.12E-02 6.20E-03 6.23E+00 7.55E-01

Stomach 4.53E-02 5.63E-03 5.52E+00 6.86E-01

Small intestine 4.51E-02 6.62E-03 5.49E+00 8.06E-01

Upper large intestine 7.16E-02 1.87E-02 8.72E+00 2.27E+00

Lower large intestine 1.72E-01 4.84E-02 2.10E+01 5.89E+00

Colon 1.15E-01 3.14E-02 1.40E+01 3.82E+00

Kidneys 4.21E-02 4.28E-03 5.13E+00 5.21E-01

Liver 3.57E-01 5.44E-02 4.35E+01 6.62E+00

Muscle 4.20E-02 5.71E-03 5.11E+00 6.95E-01

Ovaries 4.07E-02 4.70E-03 4.96E+00 5.72E-01

Pancreas 4.66E-02 4.16E-03 5.67E+00 5.07E-01

Red marrow 6.96E-01 3.14E-02 8.48E+01 3.83E+00

Extrathoracic airways 1.84E-01 1.01E-01 2.24E+01 1.23E+01

Lungs 1.09E+00 2.40E-01 1.33E+02 2.92E+01

Skin 3.80E-02 3.64E-03 4.62E+00 4.44E-01

Spleen 4.58E-02 3.56E-03 5.58E+00 4.33E-01

Testes 3.72E-02 2.73E-03 4.53E+00 3.33E-01

Thymus 5.12E-02 6.20E-03 6.23E+00 7.55E-01

Thyroid 4.23E-02 1.11E+01 5.15E+00 1.35E+03

Uterus 3.98E-02 3.96E-03 4.85E+00 4.82E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 64 of 100

Table 5-5. Comparisons of committed organ doses computed using the 

SRS Site Profile assumptions with those determined using the OTIB-0054 

method for a 4,400 dpm/d chronic intake rate at 180 days decay.

Organ

Committed organ dose (mSv)

90-day intake period 30-year intake period

TBD This report TBD This report

Adrenals 4.92E-02 8.16E-03 5.99E+00 9.93E-01

Urinary bladder 4.40E-02 6.68E-03 5.36E+00 8.13E-01

Bone surface 1.58E+00 1.86E-01 1.92E+02 2.27E+01

Brain 3.75E-02 6.15E-03 4.56E+00 7.49E-01

Breast 4.74E-02 5.86E-03 5.77E+00 7.14E-01

Esophagus 5.12E-02 6.49E-03 6.23E+00 7.90E-01

Stomach 4.53E-02 7.58E-03 5.52E+00 9.23E-01

Small intestine 4.51E-02 1.10E-02 5.49E+00 1.34E+00

Upper large intestine 7.16E-02 3.05E-02 8.72E+00 3.72E+00

Lower large intestine 1.72E-01 7.81E-02 2.10E+01 9.51E+00

Colon 1.15E-01 5.05E-02 1.40E+01 6.14E+00

Kidneys 4.21E-02 7.13E-03 5.13E+00 8.68E-01

Liver 3.57E-01 1.83E-01 4.35E+01 2.23E+01

Muscle 4.20E-02 6.20E-03 5.11E+00 7.55E-01

Ovaries 4.07E-02 7.68E-03 4.96E+00 9.35E-01

Pancreas 4.66E-02 7.22E-03 5.67E+00 8.79E-01

Red marrow 6.96E-01 7.00E-02 8.48E+01 8.53E+00

Extrathoracic airways 1.84E-01 1.01E-01 2.24E+01 1.22E+01

Lungs 1.09E+00 5.00E-01 1.33E+02 6.09E+01

Skin 3.80E-02 5.39E-03 4.62E+00 6.57E-01

Spleen 4.58E-02 6.49E-03 5.58E+00 7.90E-01

Testes 3.72E-02 5.45E-03 4.53E+00 6.63E-01

Thymus 5.12E-02 6.49E-03 6.23E+00 7.90E-01

Thyroid 4.23E-02 6.22E-03 5.15E+00 7.57E-01

Uterus 3.98E-02 6.58E-03 4.85E+00 8.01E-01
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 65 of 100

Table 5-6. Comparisons of committed organ doses computed using the 

SRS Site Profile assumptions with those determined using the OTIB-0054 

method for a 4,400 dpm/d chronic intake rate at 1 year decay.

Organ

Committed organ dose (mSv)

90-day intake period 30-year intake period

TBD This report TBD This report

Adrenals 4.92E-02 1.24E-02 5.99E+00 1.51E+00

Urinary bladder 4.40E-02 1.17E-02 5.36E+00 1.43E+00

Bone surface 1.58E+00 3.15E-01 1.92E+02 3.83E+01

Brain 3.75E-02 1.03E-02 4.56E+00 1.26E+00

Breast 4.74E-02 1.03E-02 5.77E+00 1.25E+00

Esophagus 5.12E-02 1.12E-02 6.23E+00 1.36E+00

Stomach 4.53E-02 1.30E-02 5.52E+00 1.58E+00

Small intestine 4.51E-02 1.73E-02 5.49E+00 2.11E+00

Upper large intestine 7.16E-02 4.78E-02 8.72E+00 5.82E+00

Lower large intestine 1.72E-01 1.22E-01 2.10E+01 1.48E+01

Colon 1.15E-01 7.87E-02 1.40E+01 9.58E+00

Kidneys 4.21E-02 1.16E-02 5.13E+00 1.41E+00

Liver 3.57E-01 3.46E-01 4.35E+01 4.21E+01

Muscle 4.20E-02 1.06E-02 5.11E+00 1.29E+00

Ovaries 4.07E-02 1.20E-02 4.96E+00 1.46E+00

Pancreas 4.66E-02 1.21E-02 5.67E+00 1.47E+00

Red marrow 6.96E-01 1.35E-01 8.48E+01 1.65E+01

Extrathoracic airways 1.84E-01 1.44E-01 2.24E+01 1.76E+01

Lungs 1.09E+00 8.42E-01 1.33E+02 1.02E+02

Skin 3.80E-02 9.67E-03 4.62E+00 1.18E+00

Spleen 4.58E-02 1.13E-02 5.58E+00 1.37E+00

Testes 3.72E-02 1.03E-02 4.53E+00 1.25E+00

Thymus 5.12E-02 1.12E-02 6.23E+00 1.36E+00

Thyroid 4.23E-02 1.08E-02 5.15E+00 1.31E+00

Uterus 3.98E-02 1.13E-02 4.85E+00 1.37E+00
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 66 of 100

INTRODUCTION

For SRS, most of the WBC data available for the era from about 1979 through about 1989 were 

reported in units of activity. For other periods, only limited data were reported in units of activity, 

usually 40K and 137Cs. Therefore, during this period, comparison of the measured quantities of various 

radionuclides can be made. The objective of this evaluation is to assess the reasonableness of the 

radionuclide ratios in the text of this report by comparing predicted body burdens with positive in vivo

counts from SRS workers. 

Individuals who worked in the separations or waste management areas at SRS with positive 137Cs 

WBC results during the period from 1979 to 1989 were selected for evaluation. One additional worker 

from the reactor area was chosen. A fitted dose assessment using standard dose reconstruction 

techniques was made of the positive 137Cs results. Any 137Cs results above 1 nCi were treated as 

positive measurements because this is the minimum detectable activity (MDA) stated in the SRS Site 

Profile. In actuality, the MDA varied and was likely higher. The intake amount and/or rates thus 

determined were used to determine corresponding intakes of other fission and activation products 

using the ratios in this report applicable to the individual’s work location. The highest intake ratio for 

each radionuclide and decay time out of the 5 reactor types was used. For this evaluation, intake 

rates of 144Ce, 106Ru, and 95Zr/Nb were calculated. The whole-body burdens associated with these 

intakes were projected using IMBA’s “Intakes to Bioassay” function and compared to the reported 

WBC results for these radionuclides. For 95Zr/Nb, the intake ratios from this report were used for each 

radionuclide separately, and then the predicted body burdens were summed for comparison to the 

MDAs.

Often, 144Ce, 106Ru, and 95Zr/Nb were not detected (i.e., <MDA) and only the MDA was reported. 

However, in some instances the raw WBC data permit the determination of the actual <MDA result. 

Values reported on the form titled “In Vivo Count Report” (IVCR) include “DIFF,” “MDA in counts,” and 

“MDA in nCi” for each radionuclide. The DIFF value is the result, after subtraction of the contribution 

of the Compton continuum, in units of counts. By comparing that value to the MDA in both counts and 

nanocuries, a body burden result in nanocuries can be determined. Earlier forms used to record the 

WBC results reported the DIFF value but not the MDAs. For these results, generic conversion factors 

from “Evaluation of a Whole Body Count” (DuPont undated) were used to convert the DIFF value to a 

body burden in nanocuries. DIFF values less than zero were set to zero to calculate body burdens.

WBC results on the form titled “Whole Body Counter Data” do not provide DIFF values but report net 

count rates (cpm). In this case, the 40K and 137Cs net counts were used to account for the contribution 

of the Compton continuum. The following equations were used to calculate the 144Ce, 106Ru, and 

95Zr/Nb body burdens based on calibration factors from the Watts laboratory book (Watts 1962–1967) 

for WBCs before February 1964:

144Ce, nCi = (0.766)[(144Ce net cpm) – (0.824)(40K net cpm) – (0.909)(137Cs net cpm)]

106Ru, nCi = (0.543)[(106Ru net cpm) – (0.204)(40K cpm) – (0.217)(137Cs net cpm)]

95Zr/Nb, nCi = (0.215)[(Zr-95 net cpm) – (0.107)(40K cpm) – (0.175)(137Cs net cpm)]

For after January 1964, the following equations were used:

144Ce, nCi = (0.766)[(144Ce net cpm) – (1.050)(40K net cpm) – (0.627)(137Cs net cpm)]

106Ru, nCi = (0.543)[(106Ru net cpm) – (0.222)(40K cpm) – (0.235)(137Cs net cpm)]

95Zr/Nb, nCi = (0.215)[(Zr-95 net cpm) – (0.173)(40K cpm) – (0.071)(137Cs net cpm)]

ATTACHMENT A

SRS RPRT-0047 EVALUATION

Page 1 of 35
Document No. ORAUT-RPRT-0047 Revision No. 00 Effective Date: 07/23/2013 Page 67 of 100

The reported MDAs for 144Ce, 106Ru, and 95Zr/Nb and the actual unreported result, where 

determinable, were used for the comparison. Where not reported, assumed MDAs based on other 

reported MDAs for that individual were used for the comparison. In the plots, the MDAs, assumed 

MDAs, unreported results, and reported results are marked as such for comparison to the predicted 

body burden lines for each applicable solubility type for each radionuclide. It should be noted that 

unreported results often exceed the assumed MDA. In these cases, the unreported result is still 

assumed to be a <MDA result.

It is not possible to determine unreported results for all WBCs. In particular, WBCs performed on the 

hyperpure germanium (HPGe) and lithium-drifted germanium [Ge(Li)] systems in the 1980s were 

reported with the ABACOS system. The provided printout in the claimant files does not permit the 

determination of <MDA results or the MDAs where such are not explicitly provided. 

Worker 1

This individual is listed as a front line supervisor and manager in the separations area. From 1978 

through 1989, he had 19 WBCs, half of which reported 137Cs activities above the Site Profile-listed 

MDA of 1 nCi. A high (4.8 nCi) measurement on May 11, 1987, was noted in the individual’s DOE 

records as being reported at the MDA and was therefore treated as a <MDA result. The remaining six 

positive measurements, three in a row and four isolated positives, were fit with four acute intakes 

occurring on 06/17/1979, 03/04/1982, 06/21/1984, and 12/23/1985 and two chronic intakes from 

02/16/1977 through 10/19/1978 and from 05/12/1987 through 05/12/1989.

Figure A-1. Worker 1 137Cs fit.

These intakes result in predicted 144Ce body burdens that are all less than the reported MDAs. The 

predicted body burdens are also less than the assumed MDAs for Type S material, but not for Type M 

material. The predicted body burdens are also in general agreement with the unreported results 

except for one unreported result on 03/13/1979, which is above the assumed MDA and has a value of 

47 nCi. Although above the assumed MDA, the fact that this result was not reported indicates that it 

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

9,000

1978 1979 1980 1982 1983 1984 1986 1987 1988 1990

Cs-137 body burden (pCi)

WBC result MDA fit

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was below the actual MDA for that WBC. This WBC is also the first one after the end of the first 

chronic intake. The 137Cs fit was done according to normal procedures and is within the normal range 

of expected fit quality, but does underestimate the first positive 137Cs result. Due to the relatively high 

actual 144Ce MDA that must be associated with this WBC and the underestimate of the 137Cs fit, the fit 

of the 144Ce predicted body burden is reasonable.

Figure A-2. Worker 1 144Ce predicted body burdens.

The 106Ru predicted body burdens are all less than the reported or assumed MDAs and exceed the 

unreported results two-thirds of the time for all absorption types. The unreported results that are 

higher than the predicted body burdens generally trend in a similar manner and are within the 

expected uncertainty for <MDA measurements. 

The 95Zr/Nb predicted body burdens are all less than the reported or assumed MDAs except for the 

first WBC, where the actual MDA is not known. The unreported results display a similar trend as the 

predicted body burdens and are within the expected uncertainty for <MDA measurements. The one 

positive reported measurement, on 09/14/1984, was followed up with a count of the individual with a 

Ge(Li) detector and was determined to be a false positive most likely due to surface contamination.

0

10,000

20,000

30,000

40,000

50,000

1978 1979 1980 1982 1983 1984 1986 1987 1988 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-3. Worker 1 106Ru predicted body burdens.

Figure A-4. Worker 1 95Zr/Nb predicted body burdens.

Worker 2

This individual is listed as a process operator and crane supervisor in the separations area. From 

1962 through 1987, he had 20 WBCs, 16 of which reported 137Cs activities above the Site Profilelisted MDA of 1 nCi. The positive measurements in 1986 were associated with a Zr/Nb skin 

contamination incident and were not used because there was no 137Cs intake associated with the 

incident. The contemporaneous MDAs were higher than the documented results. The remaining 

positive measurements were fit with two chronic and three acute intakes. Two positive measurements 

0

2000

4000

6000

8000

10000

12000

14000

1978 1979 1980 1982 1983 1984 1986 1987 1988 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

5000

10000

15000

20000

25000

1978 1979 1980 1982 1983 1984 1986 1987 1988 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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were excluded because they were lower than contemporaneous measurements during chronic intake 

periods. The chronic intakes ran from 08/16/1954 (start of work) through 03/30/1978 and from 

11/14/1979 through 07/31/1981. The acute intakes occurred on 12/12/1975, 01/19/1979, and 

03/12/1983.

The 144Ce predicted body burdens are consistent with or exceed most of the unreported results, the 

exceptions being the WBCs associated with the 95

Zr/Nb contamination incident and one count on 

09/15/1978 that is above the assumed MDA but was not quantified by SRS. As an unquantified 

measurement, it was assumed to be <MDA for that WBC.

Figure A-5. Worker 2 137Cs fit.

The 106Ru predicted body burdens are consistent with or exceed most of the unreported results. As 

with 144Ce, the exceptions are the WBCs associated with the 95

Zr/Nb contamination incident and the 

count on 09/15/1978. In this instance, the unreported result is less than the assumed MDA and the 

difference is within the expected uncertainty for <MDA measurements.

The 95Zr/Nb predicted body burdens exceed most of the unreported results, with the exception of the 

95Zr/Nb contamination incident. Predicted body burdens that are less than the unreported results are 

within the expected uncertainty for <MDA measurements.

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

9,000

1961 1964 1967 1969 1972 1975 1978 1980 1983 1986 1988

Cs-137 body burden (pCi)

WBC result MDA fit

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Figure A-6. Worker 2 144Ce predicted body burdens.

Figure A-7. Worker 2 106Ru predicted body burdens.

0

5,000

10,000

15,000

20,000

25,000

30,000

35,000

40,000

45,000

1961 1967 1972 1978 1983 1988

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

0

5000

10000

15000

20000

25000

30000

1961 1967 1972 1978 1983 1988 1994

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

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Figure A-8. Worker 2 95Zr/Nb predicted body burdens.

Worker 3

This individual was a production specialist in the separations area. From 1968 through 1990 he had 

21 WBCs, of which 10 had reported positive 137Cs results. The data were fit with two chronic intakes 

from 04/07/1961 through 08/06/1975 and 08/07/1976 through 05/16/1978 and one acute intake on 

12/13/1983.

Figure A-9. Worker 3 137Cs fit.

0

5000

10000

15000

20000

25000

30000

35000

40000

1961 1964 1967 1969 1972 1975 1978 1980 1983 1986 1988

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

9,000

1967 1969 1972 1975 1978 1980 1983 1986 1988 1991

Cs-137 body burden (pCi)

WBC result MDA fit

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These intakes resulted in predicted 144Ce body burdens that are all less than the reported or assumed 

MDAs except for after the acute intake on 12/13/1983. After the acute intake, the predicted body 

burdens for 144Ce grossly exceeded the assumed MDAs by a factor of 10 or more. This intake is 

unrealistically large (19 μCi 137Cs) because it is assumed to have occurred 3 years before the WBC 

date due to using the default assumption of an acute intake occurring midway between the positive 

measurement and the previous measurement, which was 6 years earlier. The predicted body 

burdens generally exceed the unreported results. The unreported results that are higher than the 

predicted body burdens generally trend in a similar manner and are within the expected uncertainty 

for <MDA measurements. Unreported results that exceed the assumed MDA are still assumed to be 

<MDA values.

The 106Ru predicted body burdens exhibit the same pattern as those of 144Ce. 

The 95Zr/Nb body burdens exceed the assumed MDAs during the chronic intakes for Types F and M 

material. The large acute intake does not affect the 95Zr/Nb body burdens on the dates of the WBCs 

due to the long assumed delay between the intake and the WBC.

Figure A-10. Worker 3 144Ce predicted body burdens.

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

1967 1969 1972 1975 1978 1980 1983 1986 1988 1991

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-11. Worker 3 106Ru predicted body burdens.

Figure A-12. Worker 3 95Zr/Nb predicted body burdens.

Worker 4

This individual worked in construction and had 15 WBCs, all but three of which were above 1 nCi of 

137Cs. The positive measurements were fit with three chronic intakes from 09/07/1954 through 

06/13/1962, 06/14/1962 through 07/01/1976, and 02/25/1978 through 03/20/1987.

0

5000

10000

15000

20000

25000

30000

35000

40000

45000

50000

1967 1969 1972 1975 1978 1980 1983 1986 1988 1991

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

2000

4000

6000

8000

10000

12000

14000

1967 1969 1972 1975 1978 1980 1983 1986 1988 1991

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-13. Worker 4 137Cs fit.

The predicted body burdens for 144Ce are consistent with or exceed the unreported results. All 

predicted body burdens also are less than or consistent with reported MDAs. The first assumed MDA 

is exceeded for both solubility types, and three of the reported MDAs are exceeded for Type M 

material.

Figure A-14. Worker 4 144Ce predicted body burdens.

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

9,000

1960 1965 1970 1975 1980 1985 1990

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

1960 1965 1970 1975 1980 1985 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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The predicted body burdens for 106Ru are consistent with or exceed the unreported results. Three 

unreported results from 1975 through 1978 exceed the predicted body burdens but trend down the 

same as the predicted body burden and are within the expected uncertainty for <MDA measurements. 

Only the first assumed MDA is exceeded and only for absorption Type F.

Figure A-15. Worker 4 106Ru predicted body burdens.

The predicted body burdens for 95Zr/Nb are consistent with or exceed the unreported results and the 

assumed or reported MDAs except for the last measurement due to the rapid elimination of 95Zr/Nb 

from the body.

Figure A-16. Worker 4 95Zr/Nb predicted body burdens.

0

2000

4000

6000

8000

10000

12000

1960 1965 1970 1975 1980 1985 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

5000

10000

15000

20000

25000

30000

35000

40000

1960 1965 1970 1975 1980 1985 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Worker 5

This individual was a reactor operator/supervisor and had five WBCs, four of which were positive for 

137Cs. Three of those results were on the same day. The highest measurement was used because 

there was no indication of whether it was before or after showering. The data were fit with one 

chronic intake from 03/24/1953 through 06/15/1987.

Figure A-17. Worker 5 137Cs fit.

The predicted body burdens for 144Ce exceed both the unreported results and the reported and 

assumed MDAs by a factor of 2 or more. The 137Cs fit was performed with a chronic intake for the 

claimant’s entire employment period up to the date of the positive measurements, which is very 

favorable to the claimant.

Figure A-18. Worker 5 144Ce predicted body burden.

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

1970 1975 1980 1985 1990

Cs-137 body burden (pCi)

WBC result MDA fit

0

20,000

40,000

60,000

80,000

100,000

1970 1975 1980 1985 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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For 106Ru, the predicted body burdens also exceed the unreported results for all solubility types, with 

Type F exceeding the reported and assumed MDAs as well.

95Zr/Nb shows the same pattern as 144Ce, with all solubility types exceeding the unreported results 

and reported and assumed MDAs.

The overprediction probably results from an interruption in the chronic intake. Because of the shorter 

half-lives of 144Ce, 106Ru, and 95Zr/Nb relative to 137Cs, any interruption in the chronic intake, especially 

near the 1987 WBCs, would result in less actual activity of the 144Ce, 106Ru, and 95Zr/Nb in the body 

than predicted using the 137Cs fit. The lack of data between 1970 and 1987 makes it difficult to make 

an accurate fit during that period. 

Figure A-19. Worker 5 106Ru predicted body burden.

0

2000

4000

6000

8000

10000

12000

14000

1970 1975 1980 1985 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

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Figure A-20. Worker 5 95Zr/Nb predicted body burden.

Worker 6

This individual worked in the decontamination and decommissioning department and had 15 WBCs, 

5 of which were less than 1 nCi for 137Cs and one other noted as being reported as <MDA. On 

05/19/1986, he had three WBCs, each after showering. One reported only an MDA; therefore, the 

other two, which show as being counted at the same time but with different results, were averaged. 

The positive measurements were fit as a series of acute intakes due to a lack of a pattern in the data. 

The acute intakes were on 04/05/1983, 01/09/1984, 07/02/1984, 06/14/1986, 01/30/1987, and 

02/26/1988.

The predicted body burdens for 144Ce are all consistent with or greater than the unreported results. In 

addition, all predicted body burdens are less than the reported MDAs. Ruthenium-106 followed the 

same pattern as 144Ce. For 95Zr/Nb, some unreported results exceed the predicted body burdens but 

are within the expected uncertainty for <MDA measurements. The predicted body burdens after the 

largest acute intake on 06/14/1986 exceed the reported and assumed MDAs.

0

40000

80000

120000

160000

200000

1970 1975 1980 1985 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-21. Worker 6 137Cs fit.

Figure A-22. Worker 6 144Ce predicted body burden.

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

9,000

1980 1982 1984 1986 1988

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

90,000

1980 1982 1984 1986 1988

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-23. Worker 6 106Ru predicted body burden.

Figure A-24. Worker 6 95Zr/Nb predicted body burden.

Worker 7

This individual was a maintenance technician with four WBCs, two of which were positive for 137Cs 

and occurred on the same day (with the result of one of them reported twice). Both measurements 

were after showering and thus the average was used. The other two WBCs had 137Cs results <MDA. 

The positive measurement was fit with a single acute intake on 11/09/1988.

0

2000

4000

6000

8000

10000

12000

1980 1982 1984 1986 1988

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

10000

20000

30000

40000

50000

60000

1980 1982 1984 1986 1988

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-25. Worker 7 137Cs fit.

The 144Ce predicted body burdens exceed the unreported result and MDA values on the date of the 

positive 137Cs WBCs. No unreported results could be determined for the other dates. For 106Ru, the 

unreported result was also exceeded on the date of the positive 137

Cs WBCs. The predicted body 

burden for 95Zr/Nb on the date of the positive 137Cs WBCs is consistent with the unreported result for 

solubility Types M and S and exceeds both the unreported result and reported MDA for solubility 

Type F.

Figure A-26. Worker 7 144Ce predicted body burdens.

0

2,000

4,000

6,000

8,000

10,000

12,000

1987 1988 1989 1990

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

1987 1988 1989 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-27. Worker 7 106Ru predicted body burdens.

Figure A-28. Worker 7 95Zr/Nb predicted body burdens.

Worker 8

This individual is listed as a laborer, laboratory technician, and separations area operator. He had 

WBCs on 31 different dates. Six of the WBCs were less than 1 nCi for 137Cs and two others were 

noted as <MDA measurements. Only the third employment period beginning in 1965 was evaluated. 

On 09/22/1986, the first WBC was before showering. The second count was a Fastscan count and 

only reported an MDA value. The third measurement was a 30-minute count and had the lowest 

quantified result. The third (3.8 nCi) result was used. On 06/01/1988, the higher of the two 

0

2000

4000

6000

8000

10000

12000

1987 1988 1989 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

5000

10000

15000

20000

25000

30000

35000

1987 1988 1989 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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measurements is noted as being taken before showering and was not used. The data were fit with 

two chronic intakes from 08/16/1965 through 11/08/1985 and 11/09/1985 through 06/16/1989 and one 

acute intake on 07/25/1988. All measurements <MDA were excluded as an overestimate. 

Figure A-29. Worker 8 137Cs fit.

Predicted body burdens for 144Ce are consistent with or exceed the unreported results after 1978. 

Before 1979, the unreported results exceed the predicted body burdens but are within the expected 

uncertainty for <MDA measurements. For 106Ru and 95Zr/Nb, the predicted body burdens exceed or 

are consistent with the unreported results. All predicted body burdens are less than the assumed or 

reported MDAs except immediately after the acute intake.

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

9,000

10,000

1965 1970 1975 1980 1985 1990

Cs-137 body burden (pCi)

WBC result MDA fit

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Figure A-30. Worker 8 144Ce predicted body burdens.

Figure A-31. Worker 8 106Ru predicted body burdens.

0

5,000

10,000

15,000

20,000

25,000

30,000

35,000

40,000

1965 1970 1975 1980 1985 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

0

5000

10000

15000

20000

25000

30000

1965 1970 1975 1980 1985 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

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Figure A-32. Worker 8 95Zr/Nb predicted body burdens.

Worker 9

This individual worked as an emergency duty officer and had 21 WBCs, all but one of which reported 

137Cs values greater than 1 nCi, including the baseline measurement on the first day of work. This 

baseline measurement was excluded. The positive measurements were fit with three chronic intakes 

from 01/08/1962 through 07/14/1964, 07/15/1964 through 08/04/1982, and 09/15/1983 through 

10/05/1988. On 03/31/1987, he had two WBCs, the first of which only reported the MDA. The second 

WBC reported an actual result and was used.

0

5000

10000

15000

20000

25000

30000

35000

40000

1965 1970 1975 1980 1985 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-33. Worker 9 137Cs fit.

The 144Ce predicted body burdens exceed all the unreported results and are less than the reported or 

assumed MDAs except in the 1960s. For 106Ru, the predicted body burdens exceed or are consistent 

with the unreported results. Like 144Ce, the 106Ru predicted body burdens are less than the reported 

or assumed MDAs except in the 1960s. For 95Zr/Nb, the predicted body burdens exceed the 

unreported result and are consistent with the assumed or reported MDAs except in the 1960s.

Figure A-34. Worker 9 144Ce predicted body burdens.

0

2,000

4,000

6,000

8,000

10,000

12,000

14,000

16,000

18,000

1960 1965 1970 1975 1980 1985 1990

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

1960 1965 1970 1975 1980 1985 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-35. Worker 9 106Ru predicted body burdens.

Figure A-36. Worker 9 95Zr/Nb predicted body burdens.

Worker 10

This individual worked as an electrical instrument mechanic and had six WBCs. All but one were less 

than 1 nCi 137Cs or were reported as <MDA measurements. On 07/08/1986, the first result was noted 

as a preliminary result and was not used. The positive measurement was fit with a single acute intake 

on 05/31/1985.

0

2000

4000

6000

8000

10000

12000

14000

1960 1965 1970 1975 1980 1985 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

5000

10000

15000

20000

25000

30000

1960 1965 1970 1975 1980 1985 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-37. Worker 10 137Cs fit.

The predicted body burdens for 144Ce and 106Ru all exceed the unreported results and are less than all 

reported and assumed MDAs. The 95Zr/Nb results are all less than the reported and assumed MDAs.

Figure A-38. Worker 10 144Ce predicted body burdens.

0

1,000

2,000

3,000

4,000

5,000

6,000

1985 1986 1987 1988 1989

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

90,000

1985 1986 1987 1988 1989

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-39. Worker 10 106Ru predicted body burdens.

Figure A-40. Worker 10 95Zr/Nb predicted body burdens.

Worker 11

This individual worked as a technician and inspector and is noted in the records as eating venison. 

The claim has been evaluated without accounting for the consumption of wild game. He had nine

WBCs, all of which had 137Cs results greater than 1 nCi. The measurements were fit with three

chronic intakes from 03/15/54 through 12/06/1960, 12/07/1960 through 10/07/1980, and 10/08/1980 

through 03/13/1990. On 03/13/1990, he had two WBCs, both before showering. The average value 

was used.

0

5000

10000

15000

20000

25000

1985 1986 1987 1988 1989

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

1000

2000

3000

4000

5000

6000

7000

8000

9000

10000

1985 1986 1987 1988 1989

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-41. Worker 11 137Cs fit.

The 144Ce predicted body burdens exceed the unreported results except for one measurement for 

Type S material. All Type M predicted body burdens also exceed the assumed and reported MDAs. 

Type S predicted body burdens are consistent with or exceed the assumed and reported MDAs. For 

106Ru, one unreported result exceeds the predicted body burden, but the difference is within the 

expected uncertainty for <MDA measurements. The 95Zr/Nb predicted body burdens exceed all the 

unreported results and assumed and reported MDAs. 

Figure A-42. Worker 11 144Ce predicted body burdens.

0

2,000

4,000

6,000

8,000

10,000

12,000

14,000

1960 1965 1970 1975 1980 1985 1990

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

90,000

1960 1965 1970 1975 1980 1985 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-43. Worker 11 106Ru predicted body burdens.

Figure A-44. Worker 11 95Zr/Nb predicted body burdens.

Worker 12

This individual worked as a firefighter/emergency medical technician/first responder and had six

WBCs before 1991 on four different dates. It was also noted that he ate venison. No adjustment was 

made for the venison consumption. There were four positive 137

Cs measurements on two dates. The 

average of the measurements on each date was used for the evaluation. The positive measurements 

were fit with two acute intakes.

0

2000

4000

6000

8000

10000

12000

14000

16000

1960 1965 1970 1975 1980 1985 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

5000

10000

15000

20000

25000

30000

35000

40000

45000

50000

1960 1965 1970 1975 1980 1985 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Figure A-45. Worker 12 137Cs fit.

All predicted body burdens for 144Ce, 106Ru, and 95Zr/Nb are consistent with or exceed the unreported 

results. The predicted body burdens are also all equal to or less than the reported or assumed MDAs 

for 106Ru. The 144Ce and 95Zr/Nb predicted body burdens exceed or are consistent with the reported 

MDAs.

Figure A-46. Worker 12 144Ce predicted body burdens.

0

1,000

2,000

3,000

4,000

5,000

6,000

7,000

8,000

1986 1987 1988 1989 1990

Cs-137 body burden (pCi)

WBC result MDA fit

0

10,000

20,000

30,000

1986 1987 1988 1989 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-47. Worker 12 106Ru predicted body burdens.

Figure A-48. Worker 12 95Zr/Nb predicted body burdens.

Worker 13

This individual is listed as a production operator primarily in waste management operations. It was 

also noted that he ate venison. From 1984 through 1988, he had 20 WBCs, most of which had 137Cs 

results above 1 nCi. Several of the WBCs noted that the measurements were taken before the 

individual showering; these results were excluded. In addition, there were multiple counts on the 

same day on multiple occasions. The average of the after-shower results was used for the 

0

2000

4000

6000

8000

10000

12000

1986 1987 1988 1989 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

5000

10000

15000

20000

25000

30000

1986 1987 1988 1989 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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evaluation. The resulting data were fit by four acute intakes occurring on 07/27/1984, 10/09/1985, 

03/14/1986, and 04/23/1988.

Figure A-49. Worker 13 137Cs fit.

The 144Ce predicted body burdens exceed all the unreported results and also exceed the reported 

MDAs during 1986 with the exception of one abnormally high reported MDA. The unreported results 

do show a higher trend during the 1985-to-1986 period when the predicted body burdens are also 

elevated. Ruthenium-106 exhibits a similar pattern with the predicted body burdens following the 

same trend as the unreported results while still remaining consistent with or higher than the 

unreported results. 

The WBCs performed in 1986 used systems capable of distinguishing between 95Zr and 95Nb and 

reported the values separately. The 95Nb MDAs are significantly lower than the 95Zr MDAs. Both sets 

of MDAs are reported. The assumed MDAs are based on the assumed MDA for WBC systems 

measuring both at the same time. Likewise, the predicted body burdens and unreported results are 

for the combined 95Zr/Nb body burdens. The unreported results follow the same trend as those for 

144Ce and 106Ru. The predicted body burdens are consistent with the unreported results and are 

within the expected uncertainty for <MDA measurements for the unreported results that are higher 

than the predicted body burdens.

0

5,000

10,000

15,000

20,000

25,000

30,000

35,000

1983 1984 1984 1985 1985 1986 1987 1987 1988 1988 1989

Cs-137 body burden (pCi)

WBC result MDA fit

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Figure A-50. Worker 13 144Ce predicted body burdens.

Figure A-51. Worker 13 106Ru predicted body burdens.

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

90,000

100,000

1983 1984 1985 1986 1987 1988

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

0

5000

10000

15000

20000

25000

30000

1983 1984 1985 1986 1987 1988

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

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Figure A-52. Worker 13 95Zr/Nb predicted body burdens.

Worker 14

This individual worked as a mail clerk and health physics technician and supervisor and had 34 

WBCs, not including recounts conducted the same day, only four of which reported less than 1 nCi of 

137Cs. The positive measurements were fit with four chronic intakes from 06/14/1954 through 

05/26/1967, 05/27/1967 through 03/28/1968, 03/29/1968 through 08/27/1979, and 08/27/1980 

through 12/31/1982, and a single acute intake on 05/25/1989.

Figure A-53. Worker 14 137Cs fit.

0

5000

10000

15000

20000

25000

30000

35000

1983 1984 1985 1986 1987 1988

Zr-Nb-95 Body Burden (pCi)

Zr-95 WBC MDA Nb-95 WBC MDA Assumed MDA Unreported result

Reported result Zr/NB sum S Zr/NB sum M F prediction

0

5,000

10,000

15,000

20,000

25,000

30,000

35,000

40,000

45,000

1960 1965 1970 1975 1980 1985 1990

Cs-137 body burden (pCi)

WBC result MDA fit

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The 144Ce predicted body burdens and unreported results generally trend in a similar manner. 

Notably, both spike upwards in 1967 and 1968 then decline. The predicted body burdens consistently 

exceed the unreported results except for 1978 to 1980 when Type S material results are less than the 

unreported results. The 106Ru predicted body burdens exceed or are consistent with all but one 

unreported results and also exceed the reported positive results in 1967 and 1968. The trend of the 

positive results in this period is the same as that for the predicted body burdens. The 95Zr/Nb 

predicted body burdens are consistent with or exceed the unreported results and are within the 

expected uncertainty for <MDA measurements where they are not exceeded.

The WBC on 06/13/1972 had reported positive results for 144Ce, 106Ru, and 95Zr/Nb. The 106Ru and 

95Zr/Nb were also positive on the follow-up count 2 days later. From these results, it appears that an 

acute intake occurred on or about 06/13/1972. The 137Cs results during this period are relatively 

consistent and do not show a significant increase on this date. Therefore, the 137Cs data were fit with 

a chronic intake during this period. This results in predicted body burdens for 144Ce, 106Ru, and 

95Zr/Nb indicative of a chronic intake rather than what one would expect for an acute intake. While the 

body burdens on these specific results are under-predicted, the integrated body burden over the 

course of the chronic intake exceeds the integrated body burden that would be obtained by fitting 

these results with an acute intake on or shortly before 06/13/1972. The total dose from 144Ce, 106Ru, 

and 95Zr/Nb is approximately proportional to the integrated body burden; therefore, the fit with a 

chronic intake is favorable to the claimant. During an actual dose reconstruction, these positive 

results would be modeled, and dose calculated separately, from the application of OTIB-0054 to the 

137Cs fits, which would also increase the assigned dose.

Figure A-54. Worker 14 144Ce predicted body burdens.

0

10,000

20,000

30,000

40,000

50,000

60,000

70,000

80,000

1960 1965 1970 1975 1980 1985 1990

Ce-144 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result

Reported result S prediction M prediction

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Figure A-55. Worker 14 106Ru predicted body burdens.

Figure A-56. Worker 14 95Zr/Nb predicted body burdens.

CONCLUSIONS

The predicted body burdens of 144Ce, 106Ru, and 95Zr/Nb due to the calculated intakes of 137Cs and 

application of the radionuclide ratios in this document are generally greater than or consistent with the 

unreported results. In some instances, the unreported results are greater than the predicted body 

burden, but the difference is largely within the expected uncertainty for <MDA measurements. Only 

isolated instances, as discussed above, had unreported results significantly greater than the predicted 

body burdens. 

0

5000

10000

15000

20000

25000

30000

1960 1965 1970 1975 1980 1985 1990

Ru-106 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

S prediction M prediction F prediction

0

10000

20000

30000

40000

50000

60000

1960 1965 1970 1975 1980 1985 1990

Zr-Nb-95 Body Burden (pCi)

WBC MDA Assumed MDA Unreported result Reported result

Zr/NB sum S Zr/NB sum M F prediction

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Claims for which the individual was known to have consumed venison or wild game were included in 

this evaluation. For these individuals, application of the ratios in this document is not necessarily 

appropriate because these individuals’ 137Cs body burdens are affected by the ingestion of 137Cs that 

is not associated with an occupational intake. The same is true for individuals for whom some 

contribution of their body burden is due to fallout from atmospheric weapons testing. Application of 

the ratios to the calculated inhalation intakes for these individuals is a conservative measure because 

these “associated” radionuclides are not truly associated with the 137Cs intakes for these individuals.

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